WorldWideScience

Sample records for reaktora tipa vvehr

  1. Possibilities for power reactor structural material and fuel testing in reactor RA; Mogucnosti reaktora RA za testiranje konstrukcionih materijala i goriva energetskih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Lazarevic, Dj; Stefanovic, D; Cupac, S; Pesic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-05-15

    Nuclear reactor RA at Vinca has been designed as a high flux general purpose research reactor. Among other it was intended to play a role of material testing reactor. A scope of activities of Material Laboratory and Reactor RA Department of Boris Kidric Institute is presented in this report. Reactor RA capacity for reactor structural material and fuel irradiation is also described. The increase of RA reactor irradiation capacity is based on the improvement of VISA type fuel channel for fast neutron irradiations, as well as on the general neutron flux increase, due to introduction of highly enriched uranium fuel into reactor core and the advanced in-core fuel management. The irradiation capacities described allow for the reactor material and fuel testing to the considerable extent. Istrazivacki reaktor RA u Vinci je projektovan kao visokofluksni istrazivacki reaktor opste namene. Pored ostalog, on je namenjen i za testiranje reaktorskih konstrukcionih materijala i goriva. U radu je dat pregled aktivnosti Laboratorije za materijale IBK i reaktora RA na tom podrucju, kao i opis povecanih mogucnosti reaktora RA za ozracivanje reaktorskih materijala i goriva u cilju njihovog testiranja. Povecanje mogucnosti reaktora RA zasniva se na usavrsavanju specijalnog gorivnog kanala tipa VISA (za ozracivanje materijala brzim neutronima), kao i na opstem povecanju neutronskog fluksa na osnovu uvodjenja i nacina koriscenja visokoobogacenog uranskog goriva u reaktoru RA. Opisane mogucnosti reaktora RA dozvoljavaju u znatnoj meri ispitivanje konstrukcionih materijala i goriva energetskih reaktora.

  2. Purification of cooling water for nuclear reactors using ion exchangers; Preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca

    Energy Technology Data Exchange (ETDEWEB)

    Ruvarac, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    Zirconiumphosphate, zirconiumoxide and natural magnetite as inorganic substances with favourable adsorption properties were the subject of investigations dealing with problems of water purification for nuclear rector cooling. Study on adsorption of impurities form reactor water to 300 deg C and 100 Atm was done by specially constructed autoclaves. On the other hand, a pre-project covering a laboratory plant for investigation of inorganic ion exchangers under real dynamic conditions is given. In order to obtain necessary data on the basis of which techno-economical analyses regarding utilization of zirconiumphosphate, zirconiumoxide and magnetite for water purification is cooling the reactors types BWR and PWR, could be performed, systematic investigations of physical and chemical properties of these substances were commenced. Equilibrium constants have been determined for adsorption processes at different pH values, as well as under various temperatures. Obtained equilibrium constants were used for calculation of thermodynamic quantities {delta}H, {delta}G and {delta}S (author) [Serbo-Croat] Cirkonijumfosfat, cirkonijumoksid i prirodni magnet, kao neorganski materijali sa pogodnim adsorpcionim osobinama, bili su predmet istrazivanja vezanih za probleme preciscavanja vode za hladjenje nuklearnih reaktora. Izucavanje adsorpcije necistoca iz reaktorske vode do 300 deg C i 100 Atm vrseno je pomocu specijalno konstruisanog autoklava, a za ispitivanje neorganskih jonoizmenjivaca pri realnim dinamickim uslovima dat je idejni projekt jednog laboratorijskog postrojenja. Za dobijanje potrebnih podataka, na osnovu kojih se mogu napraviti tehno-ekonomske analize o koriscenju cirkonijumfosfata, cirkoijumoksida i magnetita za preciscavanje vode za hladjenje reaktora tipa BWR i PWR, zapoceto je sa sistematskim proucavanjima fizickih i hemijskih osobina pomenutih materijala, odredjivane su konstante ravnoteze za procese adsorpcije pri razlicitim pH vrednostima, kao i na razlicitim

  3. Maximum neutron flux at thermal nuclear reactors; Maksimum neutronskog fluksa kod termalnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1968-10-15

    Since actual research reactors are technically complicated and expensive facilities it is important to achieve savings by appropriate reactor lattice configurations. There is a number of papers, and practical examples of reactors with central reflector, dealing with spatial distribution of fuel elements which would result in higher neutron flux. Common disadvantage of all the solutions is that the choice of best solution is done starting from the anticipated spatial distributions of fuel elements. The weakness of these approaches is lack of defined optimization criteria. Direct approach is defined as follows: determine the spatial distribution of fuel concentration starting from the condition of maximum neutron flux by fulfilling the thermal constraints. Thus the problem of determining the maximum neutron flux is solving a variational problem which is beyond the possibilities of classical variational calculation. This variational problem has been successfully solved by applying the maximum principle of Pontrjagin. Optimum distribution of fuel concentration was obtained in explicit analytical form. Thus, spatial distribution of the neutron flux and critical dimensions of quite complex reactor system are calculated in a relatively simple way. In addition to the fact that the results are innovative this approach is interesting because of the optimization procedure itself. [Serbo-Croat] Savremeni reaktori za fizicka i tehnoloska istrazivanja predstavljaju tehnicki komplikovanu i skupu masinu. Iz tog razloga su opravdana nastojanja da se podesnim rasporedom goriva u jezgru reaktora dodje do sto ekonomicnijeg rjesenja. U literaturi postoji vise radova, cak i konkretnih realizacija u vidu reaktora sa reflektorom u centru, koji se bave odredjivanjem takve prostorne zavisnosti koncentracije goriva koja pod odredjenim uslovima daje najveci neutronski fluks. Zajednicki nedostatak svih pomenutih rjesenja je u tome sto se polazi od pretpostavljenih prostornih distribucija

  4. Regulations for RA reactor operation; Propisi nuklearnog reaktora 'RA'

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-09-15

    Regulations for RA reactor operation are written in accordance with the legal regulations defined by the Law about radiation protection and related legal acts, as well as technical standards according to the IAEA recommendations. The contents of this book include: fundamental data about the reactor; legal regulations for reactor operation; organizational scheme for reactor operation; general and detailed instructions for operation, behaviour in the reactor building, performing experiments; operating rules for operation under steady state and accidental conditions. [Serbo-Croat] Propisi o radu nuklearnog reaktora RA pisani su tako da svi zakonski propisi definisani 'Zakonom o zastiti od jonizujuceg zracenja' i pratecim propisima (devet pravilnika) kao i tehnicke norme prema preporukama MAAE budu postovani u punoj meri pri radu reaktora. Sadrzaj ove knjige obuhvata: osnovne podatke o reaktoru; zakonske propise; organizaciju rada reaktora RA; opste propise o rezimu rada, kretanju u zgradi reaktora, izvodjenju eksperimenata; pogonske propise za rad u normalnom rezimu i u slucaju udesa.

  5. Two-channel model for dynamic analysis of GCR type reactor, Mathematical model; Dvokanalni model za dinamicku analizu reaktora GCR tipa, formulacija matematickog modela

    Energy Technology Data Exchange (ETDEWEB)

    Bingulac, B; Lazarevic, B; Matausek, M; Radanovic, Lj [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    A two-channel model for reactor dynamic analysis was developed. It enables representation of time dependent behaviour of a reactor as a whole and to obtain time and space dependent changes of temperature in any of the reactor channel. Model is suitable for follow-up of phenomena in limited time intervals up to few tens of minutes, since long term variations caused by fuel burnup and fission products are not taken into account in the model. Parameters are defined to cover the reactor power range from minimum to maximum. Model describes two main processes in the reactor: power generation dependent on the neutron flux and cooling.

  6. Model for spatial synthesis of automated control system of the GCR type reactor; Model za prostornu sintezu sistema automatskog upravljanja reaktora GCR tipa

    Energy Technology Data Exchange (ETDEWEB)

    Lazarevic, B; Matausek, M [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

    1966-07-01

    This paper describes the model which was developed for synthesis of spatial distribution of automated control elements in the reactor. It represents a general reliable mathematical model for analyzing transition states and synthesis of the automated control and regulation systems of GCR type reactors. One-dimensional system was defined under assumption that the time dependence of parameters of the neutron diffusion equation are identical in the total volume of the reactor and that spatial distribution of neutrons is time independent. It is shown that this assumption is satisfactory in case of short term variations which are relevant for safety analysis.

  7. Diagrams about RA reactor operation, Annex 7; Prilog 7 - Rad reaktora RA po godinama - dijagrami

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    This Annex 7 includes diagrams about RA reactor operation (MWh) from 1960-1975; mean values of reactor power per day and month in 1975, and percent of utilisation of experimental space during 1975. [Serbo-Croat] Ovaj prilog sadrzi dijagrame o radu reaktora (MWh) po godinama (1960-1975); srednje vrednosti dnevne snage reaktora u 1975. godini; rad reakrora (MWh) po mesecima u 1975; procenat iskoriscenja eksperimentalnog prostora u 1975. godini.

  8. Problems of space-time behaviour of nuclear reactors; Problemi prostorno-vremenskog ponasanja nuklearnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

    1966-07-01

    This paper covers a review of literature and mathematical methods applied for space-time behaviour of nuclear reactors. The review of literature is limited to unresolved problems and trends of actual research in the field of reactor physics. Dat je pregled literature i matematickih metoda koje se koriste prilikom tretiranja prostorno-vremenskog ponasanja nuklearnih reaktora. Pregled literature ogranicen je na jos neresene probleme i pravce u kojima su danas usmerena istrazivanja u ovoj oblasti fizike nuklearnih reaktora (author)

  9. Safety analysis of RA Reactor operation I-III; Analiza sigurnosti rada Reaktora RA I - III, IZ-213-0322-1963

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This safety analysis report covers the following three parts: Technical and operational characteristics of the RA reactor; Accidents analysis; and Environmental effects of the maximum possible accident. [Serbo-Croat] Ovaj izvestaj o analizi sigurnosti rada reaktora RA sastoji se od tri dela: Tehnicke i pogonske karakteristike reaktora RA; Analiza akcidenta; i Posledice maksimalno moguceg akcidenta na okolinu reaktora.

  10. Research in nuclear reactor theory and experimental reactors; Istrazivanja u teoriji nuklearnih reaktora i ekspeimentalni reaktori

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Elektrotehnicki fakultet, Beograd (Yugoslavia)

    1978-05-15

    The paper is devoted to the possibilities of using experimental reactors for scientific research in nuclear power with a stress on problems in nuclear reactor theory. The stationary and nonstationary neutron fields, burnup prediction and analyses as well as fuel element development and the corresponding role of test-reactors were dealt with. It was shown that the investigations in nuclear reactor theory in Yugoslavia were developing continuously and in a useful interaction with experiments on research reactors. The needs for continuing the work on fundamental problems in neutron transport theory and on improving the calculation methods for thermal power reactors, together with the improvement of performances of existing research systems, were pointed out. A new quality in scientific work could be obtained dealing with the problems connected to a possible introduction of test-reactors, and fast systems later on. It was also pleaded for the corresponding orientations in fundamental sciences. (author) Rad je posvecen mogucnostima koriscenja eksperimentalnih reaktora za naucna istrazivanja u nuklearnoj energetici, sa akcentom na probleme teorije nuklearnih reaktora. Obradjena su stacionarna i nestacionarna neutronska polja, predikcija i analize sagorevanja, kao i razvoj gorivnih elemenata te uloga test-reaktora u osvajanju njihove tehnologije. Pokazano je da su se istrazivanja u teoriji nuklearnih reaktora u nas odvijala kontinualno i u korisnoj interakciji sa eksperimentima na istrazivackim reaktorima. Istaknuta je potreba nastavljanja rada na fundamentalnim problemima transportne teorije neutrona i na usavrsavanju metoda proracuna termalnih enerrgetskih reaktora, uz poboljsanje performansi postojecih istrazivackih sistema. Novi kvalitet u naucnom radu bi predstavljala orijentacija na probleme vezane sa eventualnim uvodjenjem test-reaktora, a zatim i brzih sistema. Pledirano je i za odgovarajuca usmeravanja u fundamentalnim naukama. (author)

  11. RA reactor kinetic parameters - Progress report; Kineticki parametri reaktora RA - Izvestaj o napredovanju -

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Obradovic, D; Jevtovic, V; Velickovic, Lj [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    The objective of nuclear reactor kinetics study is to analyze the stability of reactor operation in practice. The obtained parameters should define the needed properties of automatic control system relevant for the stability of the designed reactor system. Refining the analytical models is done by using the analysis and interpretation of experimental data. Results of measured the reactor response obtained by using the reactor oscillator ROB-1 are explained by using the space independent model of the zero power reactor, by power reactor model with one feedback circuit, and by a complex model. It was assumed that the perturbations of the system are small and that linearized kinetic equations could be used. Linearized kinetic equation of the reactor system are transformed into the frequency region in order to analyze the measured values directly. The objective of this paper is to measure the RA reactor kinetics parameters, and analyze the stability of reactor operation at power levels high than nominal. Istrazivanja u oblasti kinetike nuklearnih reaktora imaju za cilj da dovedu analizu stabilnosti rada reaktora na nivo 'radne tehnologije'. Dobijeni pararametri treba da specificiraju potrebne karakteristike sistema automatske kontrole za odgovarajucu stabilnost projektovanog reaktorskog sistema. Doterivanjem analitickih modela do takvog nivoa da se zapazeni fenomeni mogu anailitcki predvideti ide preko analize i interpretacije eksperimentalnih podataka. Eksperimentalni rezultati merenja odziva reaktora, izvedeni reaktorskim oscilatorom ROB-1, interpretirani su na osnovu prostorno nezavisnog modela za reaktor nulte snage, modelom reaktora snage sa jednim kolom povratne sprege, kao i kompleksnim modelom. U ovom radu se poslo od toga da su perturbacije parametara sistema male, pa se mogu upotrebiti linearizovane kineticke jednacine. Linearizovane kineticke jednacine reaktorskog sistema transformirane su u frekventno podrucje s ciljem direktne analize mernih rezultata

  12. IV Training program for the staff of the laboratory for the RA reactor exploitation; IV Programi obuke osoblja Laboratorije za eksploataciju reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    All the staff members of the laboratory for RA reactor exploitation are obliged to learn the following: fundamental properties of the RA reactor, the role and functionality of the reactor components, basic and auxiliary reactor systems, basics of radioactivity, measures for preventing contamination. The personnel working in shifts must be acquainted with the regulations and instructions for reactor operation. Training programs for reactor operators, mechanics, electricians, instrumentators and dosimetrysts are described separately. Svi saradnici Laboratorije za eksploataciju reaktora RA moraju poznavati sledece oblasti: Osnovne karakeristike reaktora RA, princip rada, ulogu i funkcionisanje komponenti reaktora, osnovnih i pomocnih sistema reaktora; osnovne pojmove o radioaktivnom zracenju, mere za sprecavanje kontaminacije. Osoblje koje radi u smenama mora dodatno poznavati propise i uputstva za rad reaktora. Posebno je naveden program obuke operatora reaktora, mehanicara, electricara, instrumentatora, dozimetrista.

  13. Determination of the Effectiveness of Control Rods in the VVER Reactor Fuel Assemblies; Determination de l'Efficacite des Barres de Reglage dans les Ensembles Combustibles du reacteur VVER; Opredelenie ehffektivnosti reguliruyushchikh sterzhnej v sborkakh reaktora VVEHR; Determinacion de la Eficacia de las Barras de Control en los Conjuntos de Elementos Combustibles del Reactor VVER

    Energy Technology Data Exchange (ETDEWEB)

    Semenov, V. N.; Lunin, G. L.; Komissarov, L. V.; Kamyshan, A. N.; Halizev, V. I.; Andrianov, G. Ja.; Voznesenskij, V. A.; Kuz' micheva, V. A.; Lebedev, V. I. [Ordena Lenina Institut Atomnoj Energii Im. I.V. Kurchatova, Moskva, SSSR (Russian Federation)

    1964-06-15

    The paper describes experiments done in homogeneous mock-ups of the fuel assemblies from the VVER Reactor (at one level of enrichment) to determine the effectiveness of absorbing systems comprising shim fuel assemblies or water cavities and of absorbing rods clad in jackets made of differing materials. The paper also gives data on some experiments that have been done in mock-ups of assemblies with differing levels of enrichment. These experiments make it possible to verify the methods used in calculation and to evaluate the prospects of using them for heterogeneous reactors. (author) [French] Le memoire decrit les experiences qui ont ete faites pour determiner l 'efficacite des absorbants contenus dans les barres de compensation, l'effet cavitaire et l 'efficacite des absorbants gaines de materiaux divers, au moyen d'assemblages homogenes de cartouches de combustible du reacteur VVER (reacteur de puissance ralenti et refroidi a l 'eau ayant le meme taux d'enrichissement. On y trouve en outre des donnees sur certaines experiences executees a l 'aide d'assemblages de cartouches de combustible taux d'enrichissement differents. Ces travaux permettent de verifier la methode de calcul et d'evaluer ses possibilites d'application aux reacteurs non homogenes. (author) [Spanish] Se describen en la memoria experimentos para determinar la eficacia de los materiales absorbentes contenidos en las barras de compensacion, el efecto de cavitacion y la eficacia de los materiales absorbentes revestidos de diversos materiales, realizados con ayuda de los conjuntos homogeneos de elementos combustibles del reactor VVER (reactor de potencia moderado y refrigerado por agua) con un solo grado de enriquecimiento. Ademas, se exponen datos sobre los experimentos efectuados con ayuda de conjuntos de grados de enriquecimientos; variados. Tales experimentos permiten verificar el metodo de calculo teorico, utilizad o y evaluar la posibilidad de aplicarlo a los reactores no homogeneos. (author) [Russian] V doklade opisyvajutsja jeksperimenty po opredeleniju jeffektivnosti poglotitelej kompensirujushhih kasset vodjanyh polostej i poglotitelej kompensirujushhih k a s set vodjanyh polostej i poglotitelej s chehlami iz razlichnyh materialov na odnorodnyh sborkah, sostojashhih iz kasset s razlichnym obogashheniem. Krome t o go , privodjatsja dannye po nekotorym jeksperimentam na sborkah iz kasset s razlichnym obogashheniem. Jeti jeksperimenty pozvoljajut proverit' metodiku ra sch eta i ocenit' vozmozhnosti ee primenenija dlja neodnorodnyh reaktorov . (author)

  14. Chemical dosimetry of the RA reactor at Vinca, Yugoslavia; Hemijska dozimetrija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Gal, O; Markovic, V; Radak, B [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    The ten-year work on in-pile chemical dosimetry of the Radiation chemistry Department at the Boris Kidric Institute at Vinca is reviewed. As an introduction, the general theory of the dosimetry of two-component radiation field is given and the uses of the derived equations in calorimetry and chemical dosimetry have been discussed. The chemical systems worked out for the in-pile use: solid oxalic acid and their solutions in light and heavy water, are then described and also the procedures of their use. The latter two are treated as a double system particularly suitable for two-component radiation fields. Finally, the limitations in use are discussed and some other systems, the study of which is in progress, mentioned (malonic and succinic acid) (author) [Serbo-Croat] Merenje energije koju apsorbuje sistem izlozen zracenju sastavni je deo svakog radijaciono-hemijskog eksperimenta. Time se moze objasniti veliki interes za koriscenje postojecih i razvijanje novih metoda dozimetrije u laboratorijama koje se bave radijacionom hemijom. Poslednjih godina posebna paznja se posvecuje dozimetriji vrlo visokih doza (10{sup 2}-10{sup 3} mrad) narocito onih sa kojima se radi u polju mesovitog zracenja reaktora. U laboratoriji za radijacionu hemiju Instituta 'Boris Kidric' u Vinci na dozimetriji zracenja reaktorskog jezgra radi se vec skoro 10 godina. Ta aktivnost je deo rada na hemijskoj dozimetriji uopste, kojom se bavi ova laboratorija od svog postanka (kraj 1955. godine). Sa radom na dozimetriji kod nas otpocelo se u periodu prvog podizanja na snagu reaktora RA, krajem 1959. godine. Paralelno su razvijane i primenjivane i hemijske i kalorimetrijske metode i njima vrsena dozimetrijska kalibracija reaktora. U ovom radu ucestvovalo je vise istrazivaca iz Laboratorije za radijacionu hemiju uz tesnu saradnju sa reaktorskim fizicarima i osobljem reaktora RA. Cilj ovog napisa je da sumira nas rad na hemijskoj dozimetriji reaktora. Pri tom se, najpre, zeli da ukaze na sustinu

  15. Regulations and instructions for RA reactor operation; Propisi i uputstva za pogon reaktora 'A'

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    This regulatory guide consists of following 4 chapters: Description of the RA reactor, organization scheme, regulations for performing experiments; Regulations for staff on duty; Instructions for operating the vacuum systems, heavy water and helium systems; and evacuation in case of accident. [Serbo-Croat] Ovaj pravilnik sadrzi sledeca 4 poglavlja: Opis reaktora RA, sema organizacije rada, propisi za izvodjenje eksperimenata; Pravilnik za rad dezurnog osoblja; Uputstva za rada sa vakuum sistemima, sistemom teske vode, sistemom helijuma; evakuacija u slucaju udesa.

  16. Childhood Osteoporosis and Presentation of Two Cases with Osteogenesis Imperfecta Type V / Osteoporoza V Otroški Dobi in Predstavitev Dveh Bolnikov Z Osteogenesis Imperfecta Tipa V

    Directory of Open Access Journals (Sweden)

    Bratanic Nina

    2015-03-01

    Full Text Available Uvod. Osteogenesis imperfecta (OI je vzročno heterogena bolezen, katere značilnost je osteoporoza v otroštvu. Pri vseh opisanih bolnikih s podtipom OI tipa V je vzrok bolezni ista mutacija c.-14C>T gena IFITM5. Kljub temu med bolniki obstaja izrazita fenotipska variabilnost v klinični sliki, toda opisan je le dober odgovor na zdravljenje z bisfosfonati.

  17. Nuclear Reactor RA Safety Report, Vol. 12, Accidents during reactor operation; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 12, Akcidenti u dosadasnjem radu reaktora

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    This volume includes description and analysis of typical accidents occurred during operation of RA reactor in chronological order, as follows: contamination of primary coolant circuit; leakage of heavy water from the primary coolant loop; contamination of vertical experimental channel; air contamination in the reactor building and loss of circulation of the primary coolant; failures of the vacuum pump and spent fuel packaging device; rupture of the spent fuel element cladding; dethronement's of capsule for irradiation of fuel element; rupture of the vertical experimental channel and contamination of the surroundings; swelling of a fuel element; appearance of deposits on the surface of the fuel elements cladding. The last chapter describes similar accidents occurred on nuclear reactors in the world. [Serbo-Croat] Ova knjiga sadrzi hronoloski pregled i analizu karakteristika akcidenata u dosadasnjem radu reaktora RA: kontaminacija primarnog kola hladjenja; isticanje teske vode is primarnog kola hladjenje; kontaminacija eksperimentalnog vertikalnog kanala; kontaminacija vazduha u hali reaktora i prestanak cirkulacije primarnog hladioca; otkaz vakum pumpe i uredjaja za prepakivanje ozracenog goriva; proboj kosuljice ozracenog gorivnog elementa; dehermetizacija kapsule za ozracivanje nuklearnog goriva; proboj eksperimentalnog vertikalnog kanala i kontaminacija prostorija; bubrenje gorivnog elementa; pojava taloga na kosuljicama gorivnih elemenata. Poslednje poglavlje opisuje udese na koji su se dogodili na nuklearnim reaktorima u svetu.

  18. Annex VII - Diagrams: 1. Reactor operation (1960-1977); 2. Mean daily reactor power density in 1977; 3. Monthly reactor power for 1977; 4. percent of utilization of experimental space in 1977; Prilog VII - Dijagrami: 1. Rad reaktora (MWh) po godinama (1960-1977); 2. Srednja dnevna snaga reaktora u 1977. godini; 3. Rad reaktora (MWh) po mesecima za 1977. godinu i 4. Procenat iskoriscenja eksperimentalnog prostora u 1977. godini

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-12-15

    This Annex includes the following diagrams: 1. Annual Reactor RA power production (MWh) for the period from 1960-1977; 2. Mean daily reactor power density MW in 1977; 3. Monthly reactor power production (MWh) for 1977; 4. percent of utilization of experimental space in 1977. [Serbo-Croat] Ovaj prilog sadrzi dijagrame: 1. Rad reaktora (MWh) po godinama (1960-1977); 2. Srednja dnevna snaga reaktora u 1977. godini; 3. Rad reaktora (MWh) po mesecima za 1977. godinu i 4. Procenat iskoriscenja eksperimentalnog prostora u 1977. godini.

  19. Instructions for RA reactor decontamination - Annex 10; Prilog 10 - Uputstvo za dekontaminaciju Reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-12-15

    Instructions for RA reactor decontamination includes: action plan for decontamination of the heavy water system by 7% water solution of H{sub 3}PO{sub 4} + 2% CrO{sub 3} acid; description of the preparatory work including calculation of the pipes volume and installation of special pipes; detailed instructions for decontamination procedure. [Serbo-Croat] Uputstvo za dekontaminaciju Reaktora RA sadrzi: plan operacija za dekontaminaciju sistema teske vode 7% vodenim rastvorom kiseline H{sub 3}PO{sub 4} + 2% CrO{sub 3}; opis pripremnih radova ukljucujuci proracun zapremine covovoda i montiranje posebnih cevovoda; detaljno uputstvo za izvodjenje operacija pri dekontaminaciji.

  20. Nuclear Reactor RA Safety Report, Vol. 8, Auxiliary system; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 8, Pomocni sistemi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    This volume describes RA reactor auxiliary systems, as follows: special ventilation system, special drainage system, hot cells, systems for internal transport. Ventilation system is considered as part of the reactor safety and protection system. Its role is eliminate possible radioactive particles dispersion in the environment. Special drainage system includes pipes and reservoirs with the safety role, meaning absorption or storage of possible radioactive waste water from the reactor building. Hot cells existing in the RA reactor building are designed for production of sealed radioactive sources, including packaging and transport. [Serbo-Croat] Ova knjiga obuhvata opis pomocnih sistem reaktora RA: sistem specijalne ventilacije, sistem specijalne kanalizacije, vruce komore, sistemi za unutrasnji transport. Ventilacioni sistem je znacajan deo sistema zastite i sigurnosti reaktora. Njegova je uloga da onemoguci disperziju radioaktivnih cestica u okolinu. Sistem specijalne kanalizacije sastoji se od agregata, cevovoda i rezervoara sa sigurnosnom armaturom i ima zadatak da prihvata i u sebe deponuje radioaktivne otpadne vode iz objekarta reaktora RA. U zgradi reaktora RA postoje vruce komore koje su namenjene za proizvodnju zatvorenih izvora zracenje, ukljucujuci i mehanicku obradu, prepakivanje i transport.

  1. Control Rods in high-Flux Swimming-Pool Reactors; Les Barres de Controle dans les Piles Piscines a Haut Flux; Reguliruyushchie sterzhni dlya reaktorov bassejnovogo tipa s vysokoj plotnost'yu nejtronnogo potoka; Las Barras de Control en los Reactores Tipo Piscina de Flujo Elevado

    Energy Technology Data Exchange (ETDEWEB)

    Ageroni, P.; Blum, P.; Denielou, G.; Denis, P.; Meunier, C. [Centre d' Etudes Nucleaires de Grenoble (France)

    1964-06-15

    etudes en cours sur les barres de controle des piles piscine a coeur ouvert fonctionnant dans la bande de 10 a 30 MW. (author) [Spanish] La memoria examina los problemas planteados por las barras de control en los reactores de investigacion de tipo piscina abierta, de alta potencia especifica y elevado flujo, basandose en calculos y experimentos efectuados durante la construccion del reactor SILOE. Expone asimismo la experiencia adquirida con las barras de control mientras el reactor funcionaba a 13 MW. Examina sucesivamente: a) Los balances de reactividad y los valores de esta para los diversos tipos de barras de control que se han ensayado (cadmio, B4C, tierras raras, y combinaciones de estas sustancias); b) los picos de flujo que la presencia de barras de control crea en el cuerpo del reactor, su influencia sobre la potencia especifica, los flujos rapidos que se pueden obtener y los medios para incrementarlos; c) los problemas tecnologicos planteados por la construccion de las barras; d) los problemas de refrigeracion, vibracion, deformacion y tiempo necesario para introducirlos en el reactor. Para terminar, describe someramente loe estudios que se estan realizando con las barras de control de reactores de tipo piscina de cuerpo abierto cuando funcionan en el intervalo de potencias comprendido entre 10 y 30 MW. (author) [Russian] 1. V svete raschetov i jeksperimentov, provedennyh pri postrojke reaktora STLOE , rassmatrivajutsja problemy, voznikajushhie v svjazi s regulirujushhimi sterzhnjami dlja issledovatel'skih reaktorov otkrytogo bassejnovogo tipa s bol'shoj udel'noj moshhnost'ju i s vysokoj plotnost'ju nejtronnogo potoka. Privodjatsja takzhe rezul'taty ispytanija jetogo reaktora pri .moshhnosti 13 mgvt v svjazi s razlichnymi regulirujushhimi sterzhnjami. 2. Posledov atel'no rassmatrivajutsja sledujushhie problemy: a) balans reaktivnosti i reaktivnaja sposobnost' podvergnutyh ispytanijam regulirujushhih sterzhnej razlichnyh tipov (kadmij, B{sub 4}C , redkie zemli

  2. Influence of absorbers on the reactivity of the reactor; Odredjivanje uticaja apsorbera na reaktivnost reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Influence of absorbers on the reactivity of the reactor was calculated by two-group diffusion theory applying corrections for boundary conditions derived from the transport theory because diffusion theory in not applicable in the vicinity of boundary surfaces especially in case of strong absorbers. This report shows the calculations of central absorber efficiency in the core with and without reflector, and efficiency of the group of absorbers randomly placed in the core. Approximation method for determining the efficiency of the absorber is described as well as numerical verification of results. Effective absorber dimensions and the influence of gaps on the reactor dimensions are shown. [Serbo-Croat] Uticaj apsorbera na reaktivnost reaktora racunat je primenom difuzione dvogrupne teorije uz korekcije kod primene granicnih uslova koje daje transportna teorija za efektivne dimenzije apsorbera posto difuziona teorija ne moze da primeni u blizini granicnih povrsina posebno kod jakih apsorbera. U ovom izvestaju dati su proracuni efektivnosti centralnog apsorbera u reflektovanom u nereflektovanom reaktoru, efektivnosti grupe proizvoljno ubacenih apsorbera. Dat je i prikaz aproksimativne metode za odredjivanje efektivnosti apsorbera kao i numericka provera rezultata. Prikazane su efektivne dimenzije apsorbera kao i uticaj supljina na kriticne dimenzije reaktora.

  3. Change of I-V characteristics of SiC diodes upon reactor irradiation; Modification des caracteristiques I-V de jonctions p-n au SiC du fait d'une irradiation dans un reacteur; Izmeneniya kharakteristik I-V vyrashchennogo v SiC perekhoda tipa p-n posle oblucheniya ego v reaktore; Modificaciones que sufren por irradiacion en un reactor las caracteristicas I-V de uniones p-n en SiC

    Energy Technology Data Exchange (ETDEWEB)

    Heerschap, M; De Coninck, R [Solid State Physics Dept., SCK-CEN, Mol (Belgium)

    1962-04-15

    distintas procedencias. Las uniones se obtuvieron en el horno de Lely. Midieron las caracteristicas directa e inversa durante la irradiacion, y despues de esta, hasta la temperatura de 150{sup o}C. Se estan realizando mediciones hasta 500{sup o}C. Han encontrado que uno de los tipos de diodo es resistente a los neutrones del BR-1 hasta un flujo integrado de 10{sup 15} neutrones/cm{sup 2}, mientras que el otro soporta hasta 10{sup 17} neutrones/cm{sup 2}. La memoria indica los cambios de las caracteristicas, asi como los resultados de algunos experimentos de recocido. (author) [Russian] V poiskakh poluprovodnikov, kotorye mogli by byt' ispol'zovany v reaktorakh s vysokoj plotnost'yu nejtronnogo potoka dlya izmereniya raspredeleniya potokov, my obluchali v bel'gijskom reaktore BR-1 perekhody tipa p-n v SiC. Byli oblucheny dva tipa diodov SiC razlichnogo proiskhozhdeniya. EHti perekhody vyrashchivayutsya v pechi Loli. Izmeneniya pryamoj i obratnoj kharakteristik byli izmereny posle i vo vremya oblucheniya vplot' do temperatury 150{sup o}C; v nastoyashchee vremya proizvodyatsya izmereniya vplot' do temperatury 500{sup o}C. Bylo ustanovleno, chto odin tip dioda vyderzhivaet nejtronnoe obluchenie reaktora BR-1 vplot' do integrirovannogo potoka 10{sup 15} nejtronov na kv. sm, togda kak drugoj tip vyderzhivaet obluchenie vplot' do potoka 10{sup 17} nejtronov na kv. sm. Dayutsya izmeneniya kharakteristik, a takzhe rezul'taty nekotorykh ehksperimentov otzhiga. (author)

  4. Nuclear Reactor RA Safety Report, Vol. 5, Reactor cooling systems; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 5, Hladjenje reaktora i pripadajuci sistemi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    RA reactor cooling system enable cooling during normal operation and under possible accidental conditions and include: technical water system, heavy water system, helium gas system, system for heavy water purification and emergency cooling system. Primary cooling system is a closed heavy water circulation system. Heavy water system is designed to enable permanent circulation and twofold function of heavy water. In the upward direction of cooling it has a coolant role and in the downward direction it is the moderator. Separate part of the primary coolant loop is the system for heavy water purification. This system uses distillation and ion exchange processes. [Serbo-Croat] Sistemi za hladjenje reaktora RA obezbedjuju hladjenje u svim rezimima eksploatacije i potenijalno udesnim satnjim i obuhvataju: sistem tehnicke vode, sistem teske vode, gasni sistem helijuma, sistem za preciscavanje teske vode i sistem za akcidentalno hladjenje. Primarni sistem za hladjenje je zatvoreni cirkulacioni sistem teske vode. Specificnost sistema teske vode vezana je za neprekidnost cirkulacije i razlicite funkcije teske vode. U uzlaznom strujanju, teske vode ima ulogu hladioca a u silaznom ulogu moderatora. Poseban deo primarnog sistema predstavlja sistem za preciscavanje teske vode. Ovaj sistem koristi destilacioni i jonoizmenjivacki postupak.

  5. Operation and maintenance of RA Reactor, Annual report 1977; Pogon i odrzavanje reaktora RA - Izvestaj o radu u 1977. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1977-12-15

    During 1977, the RA Reactor was operated at nominal power of 6.5 MW for 183 days. Total production was 28582 MWh which is 10% higher than planned. Second phase of introducing the 80% enriched fuel was fulfilled according to the plan. This means that the reactor core will be filled with highly enriched fuel in 1978. Refueling was done three time during the past year. After completing the first phase of the fuel exchange which was related mostly to reactor safety, the second phase will be devoted to the more efficient increase of neutron flux . This second phase is of utmost importance because higher neutron flux will provide better and more efficient reactor application from economic point of view. This will justify the application of the new more expensive highly enriched fuel. The budget for reactor operation and maintenance is hardly enough to cover the maintenance of the components and instrumentation. During 1977 there were no accidents related nor incidents related to the instrumentation or related to radiation protection. [Serbo-Croat] Reaktor RA je u toku 1977. godine ostvario rad od 28583 MWh odnosno 183 dana rada na nominalnoj snazi, sto u odnosu na plan rada iznosi 10% vise od planiranog. Druga faza uvodjenja 80% obogacenog goriva izvrsena je prema planu sto znaci da ce se punjenje jezgra reaktora 80% gorivom zavrsiti u toku 1978. godine. Izvrsene su tri izmene goriva. Posle isteka prvog dela prelaznog rezima koji je usmeren na maksimalnu sigurnost reaktora preci ce se na drugi deo usmeren na vece i brze povecanje neutronskog fluksa. Druga faza je od izuzetnog znacaja jer ce omoguciti bolje i znatno ekonomicnije koriscenje reaktora i opravdati upotrebu novog i skupljeg goriva. Sredstva za pogon i odrzavanje reaktora RA su jedva dovoljna za odrzavanje neophodnog nivoa opreme. Akcidenata u toku 1977. godine nije bilo ni sa opremom ni u pogledu zastite od zracenja.

  6. Measurement of zero power reactor dynamic response by cross correlation method; Merenje dinamickog odziva reaktora nulte snage kros korelacionom metodom

    Energy Technology Data Exchange (ETDEWEB)

    Kostic, Lj; Petrovic, M [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1969-07-15

    Pulse response is comprehensive description of linear system dynamics. In this paper, cross correlation method was used for measuring the response of zero power reactor. Reactor system was perturbed by pseudo-random signal, which was cross correlated with the reactor signal responding to this perturbation on the digital ZUSE Z-23 computer. Cross-correlation functions were measured for different positions of stochastic oscillator and ionization chamber in the critical system. From numerical processing of performed experimental data, it was concluded that a more powerful faster computer would be needed for processing statistical experiments. In that case it would be possible to obtain information about spatial effects in the reactor and propagation of neutron waves in the multiplication medium. Impulsni odziv je potpuni opis dinamike linearnog sistema. Za merenje impulsnog odziva nultog reaktora, u ovom radu, koriscena je kros korelaciona metoda. Reaktorski sistem je perturbovan pseudoslucajnim signalom, koji je u digitalnom racunaru ZUSE Z-23 kroskorelisan sa signalom odziva reaktora na ove perturbacije. Merene su kroskorelacione funkcije za razlicite polozaje stohastickog oscilatora i jonizacione komore u kriticnom sistemu. Iz numericki obradjivanih eksperimenta namece se kao zakljucak da bi za obradu statistickih eksperimenata kod nultih reaktora bio potreban racunar veceg kapaciteta i brzine. U tom slucaju bi se iz ovako postavljenog eksperimenta moglo doci i do informacija o prostornim efektima u reaktoru i prostiranju neutronskih talasa kroz multiplikativnu sredinu. (author)

  7. Operation, maintenance and utilization of the RA reactor, Annual report 1978; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1978. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    It has been planned for 1978 that the RA reactor would be operated for 158 dana at nominal power of 6.5 MW meaning production of 24 648 MWh. The plan was fulfilled since 24 652 MWh was produces. Reactor operation for 158 days is relevant to reactor operation for 200 days in the period before 1975. The reason is increased neutron flux achieved due to improved fuel management and the characteristics of the new 80% enriched fuel. At the end of 1978 the reactor core contained 45% of 80% enriched fuel elements. Increase of neutron flux has shortened the typical time needed for irradiation of the most important samples for isotope production. This significant success in reactor operation is at the same time an obligation for increasing its utilization. Some new trends proposed for increasing reactor utilization capacities were presented at the Conference on utilization of research nuclear reactors in Yugoslavia held in May 1978. [Serbo-Croat] Reaktor RA imao je u planu za 1978. godinu 158 dana rada na nominalnoj snazi od 6.5 MW, sto odgovara radu od 24 648 MWh. Ostvareno je 24 652 MWh sto znaci da je plan ostvaren. Rad reaktora od 158 dana odgovara radu reaktora od 200 dana u periodu pre 1975. godine. Razlog je povecanje neutronskog fluksa zahvaljujuci usavrsenom rukovanju gorivom i karakteristikama novog 80% obogacenog goriva. Krajem 1978. godine 45% jezgra reaktora bilo je popunjeno novim 80% obogacenim gorivom. Povecani neutronski fluks omogucio je skracenje vremena ozracivanja vaznih uzoraka za proizvodnju radioaktivnih izotopa. Ovaj znacajan uspeh je istovremeno obaveza znatno veceg iskoriscenja reaktora RA. Rezultati napora da se postigne vece iskoriscenje reaktora RA prezentirani su na Konferenciji o koriscenju nuklearnih reaktora u Jugoslaviji koja je odrzana u maju 1978.

  8. Action plan during reactor shutdown in October 1965, Annex 5; Prilog br. 5 - Plan radova u toku stajanja reaktora u mesecu oktobru 1965. godine

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The action plan of the division for reactor maintenance during reactor shutdown includes detailed list of tasks for mechanics, electronic and electrical equipment group during the reactor shutdown period in October 1965. It contains tasks for planned shutdown periods in September, August, July, May, April, March, and February 1965. [Serbo-Croat] Plan radova Odelenja odrzavanja reaktora RA za period stajanja reaktora u oktobru mesecu 1965. sadrzi detaljnu listu zadataka masinske grupe, elektro grupe i elektronske grupe. Ovaj prilog sadrzi i zadatke koji ce biti obavljeni tokom planiranih perioda kada je reaktor zaustavljen u septembru, avgustu, julu, junu, maju, aprilu, martu i februaru 1965.

  9. RA Research nuclear reactor Part 1, RA Reactor operation and maintenance in 1987; Istrazivacki nuklearni reaktor RA Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1987. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1987-12-15

    RA research reacto was not operated due to the prohibition issued in 1984 by the Government of Serbia. Three major tasks were finished in order to fulfill the licensing regulations about safety of nuclear facilities which is the condition for obtaining permanent operation licence. These projects involved construction of the emergency cooling system, reconstruction of the existing special ventilation system, and renewal of the system for electric power supply of the reactor systems. Renewal of the RA reactor instrumentation system was initiated. Design project was done by the Russian Atomenergoeksport, and is foreseen to be completed by the end of 1988. The RA reactor safety report was finished in 1987. This annual report includes 8 annexes concerning reactor operation, activities of services and financial issues, and three special annexes: report on testing the emergency cooling system, report on renewal of the RA reactor and design specifications for reactor renewal and reconstruction. [Serbo-Croat] Reaktor RA nije radio usled zabrane Izvsnog veca Skupstine Srbije od 27. avgusta 1984. U cilju povecanja pouzdanosti rada reaktora a da bi se udovoljilo zakonskim propisima sto je uslov za dobijanje stalne dozvole za rad realizovana su tri velika zahvata na reaktoru RA. Ovi zahvati obuhvatili su izgradnju sistema za hladjenje jezgra reaktora u slucaju nuzde, rekonstukciju postojeceg sistema specijalne ventilacije i rekonstrukciju sistema napajanja elektricnom energijom neophodnih potrosaca reaktora RA. Zapoceti su radovi na modernizaciji intrumentacije reaktora RA, projekat je izradjen u sovjetskoj organizaciji Atomenergoeksport, a trebalo bi da se realizuje do kraja 1989. godine. U cilju povecanja prostora za skladistenje ozracenog nuklearnog goriva i njegovog efikasnijeg koriscenja, izradjen je su projekti za rekonstrukciju postojecih uredjaja za rukovanje gorivom, povecanje smestajnog kapaciteta i preciscavanje vode u bazenima za odlezavanje. Realizaija ovih

  10. Wpływ czasu napowietrzania na pracę reaktora SBR i SBBR

    Directory of Open Access Journals (Sweden)

    Małgorzata Makowska

    2016-06-01

    Full Text Available W pracy przedstawiono efekty oczyszczania małych ilości ścieków w bioreaktorach porcjowych. Przebadano dwa równolegle pracujące reaktory, z czego jeden był klasycznym systemem SBR, a drugi to reaktor SBBR ze złożem ruchomym. Obydwa ciągi technologiczne oczyszczały taką samą ilość ścieków bytowych wstępnie podczyszczonych w piaskowniku. Trzy kolejne serie badań różniły się długością napowietrzania. Porównano pracę reaktorów w kolejnych seriach oraz analizowano wyniki uzyskane w obu systemach. Największą skuteczność usuwania związków węgla organicznego (jako ChZT i azotu (jako N-NH4 uzyskano w reaktorze SBBR w trzeciej serii badań (średnio odpowiednio 90 i 62%. Reaktor SBBR pracował bardziej stabilnie oraz usuwał na drodze biologicznej fosfor z największą średnią skutecznością 83% w serii trzeciej. Ścieki oczyszczone w tym reaktorze charakteryzowały się mniejszym stężeniem zawiesiny, co świadczy o skuteczniejszej pracy reaktora z wypełnieniem w fazie sedymentacji.

  11. RA reactor action plan for 1977 - Annex VI; Prilog VI - Plan rada reaktora RA za 1977. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-12-15

    In the RA reactor action plan for 1977 it is foreseen that the reactor would be operated for 181 days, mostly at nominal power of 6.5 MW. It is planned to produce 28236 MWh in total. Five reactor core exchanges (refuelling) are planned. The plan includes time for repair of components as well as for cooling. [Serbo-Croat] Plan rada reaktora RA predvidja rad tokom 181 dana, vecim delom na nominalnoj snazi od 6,5 MW tokom 1977. godine. Planirano je da ukupni rad iznosi 28236 MWh. Planom je predvidjeno i pet izmena goriva kao i vreme potrebno za remont opreme i hladjenje.

  12. Inducción de callos embriogénicos y formación de proembriones somáticos en Pterogyne nitens Tull "tipa colorada"

    Directory of Open Access Journals (Sweden)

    Maritza Vacca Molina

    2014-07-01

    Full Text Available Título en español: Inducción de callos embriogénicos y formación de proembriones somáticos en Pterogyne nitens Tull "tipa colorada" Título en ingles: Embriogenic calli induction and somatic proembryo  formation in Pterogyne nitens Tull Título corto: Callo embriogénico y  proembriones somáticos en Pterogyne nitens Tull Resumen: Pterogyne nitens es un árbol que crece en bosques húmedos del Norte de la Argentina. Por su calidad maderera la especie se utiliza en forestación, reforestación o enriquecimiento de bosques nativos. Una alternativa a los métodos convencionales de propagación son las técnicas de cultivo de tejidos vegetales mediante el uso de la embriogénesis somática. El objetivo del presente trabajo es inducir la formación de callos embriogénicos y la obtención de proembriones somáticos evaluando la influencia del tipo de explanto, tipo y concentración de reguladores de crecimiento y composición del medio basal. Para la inducción de callos embriogénicos se utilizan explantos  extraídos de hojas cotiledonares, foliolos, tallos y raíces de  plántulas de dos meses de edad. Se emplean tres medios de cultivos MSC, MS50 y MSMOD. Cada medio de cultivo se suplementa con 2,4-D ó ANA en distintas concentraciones. A los 45 días los explantos provenientes de hojas cotiledonares en los medios de MSC con 2,4-D en concentraciones de  67.87, 107.41, 113.12, 135.74 y 180.99 µM, se logra en mayor proporción la formación de masas callosas amarillas. Con 107.41 µM de 2,4-D en el medio MSC se observa la formación de estructuras proembrionarias. Los segmentos radiculares en todos los tratamientos evaluados, no desarrollan callos. Palabras clave: Tipa colorada, micropropagación, embriogénesis, forestales, leguminosa. Abstract: Pterogyne nitens is a tree that grows in wet forests of Northern Argentina. Due to its quality timber especies are used in afforestation, reforestation or enrichment of native forests. An

  13. Regulations for the maintenance division of the RA reactor, Annex 6; Prilog 6 - Pravilnik poslovanja Odelenja odrzavanja i remonta reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Badrljica, R [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The regulations for the Division of reactor maintenance include the organizational scheme, tasks of the Division, and operation procedures for all the staff members. [Serbo-Croat] Pravilnik o radu Odelenja za odrzavanje reaktora RA sadrzi opis organizacione strukture sluzbe, zadataka Odelenja, organizacije rada, nacin poslovanja za sve saradnike Odelenja.

  14. Operation, safety and utilization of the RA reactor in 1978 - Report; Prilog I - Rad, sigurnost i iskoriscenost reaktora RA u 1978. godini - Izvestaj

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    This report includes a review of work related to development of reactor operation capacities and increase of the RA reactor safety and economic operation. Statistical data about reactor operation and utilization are included as well. Introducing of the new 80% enriched fuel into the the reactor core enabled increase of the neutron flux, i.e. increase of its production capabilities. Safety and optimization analyses concerned with introduction of the new fuel have shown that the most safe and economic procedure was gradual introducing of the highly enriched fuel. This procedure was based on the concept of mixed core configuration with 2% and 80% enriched fuel elements. By applying this original concept the following significant savings were achieved: fuel elements savings, shortening of the annual period of reactor operation, savings in spent fuel casks, electric power savings, slowing down of heavy water degradation. [Serbo-Croat] Ovaj izvestaj sadrzi pregled o radu na razvoju eksploatacionih mogucnosti i povecanju sigurnosti i ekonomicnosti reaktora RA. Prilozeni su i statisticki podaci o radu i iskoriscenosti reaktora u 1978. godini. Uvodjenje novog 80% obogacenog goriva u jezgro reaktora omogucilo je povecanje neutronskog fluksa tj. povecanje njegovoh proizvodnih mogucnosti. Sigurnosne i optimizacione analize uvodjenja novog goriva pokazale su da je nasigurniji i najekonomicniji postupak postupnog uvodjenja visokoobogacenog goriva koji se zasniva na konceptu mesane resetke sa 2% i 80% obogacenim gorivom. Ovaj originalni koncept omogucio je da se postignu znatne ustede u gorivu, skracivanje godisnjeg rada reaktora, usteda sudova za odlaganje isluzenog goriva, usteda elektricne energije, usporavanje degradacije teske vode.

  15. Operation and maintenance of the RA nuclear reactor for 1977, Report Annex I; Rad i iskoriscenost reaktora RA u 1977. godini, izvestaj Prilog I

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1977-12-15

    RA reactor operation plan was fulfilled, meaning 28583 MWh. In addition to 183 days of operation at full power, during 1977 the reactor was operated for 14 days at lower power level according to the demand of users. The utilization level of rector irradiation capability (neutron flux and time of operation) was 14%. This annex includes detailed statistical data about reactor operation, utilization, power level, savings concerned with new 80% enriched fuel. All the 9 vertical experimental channels were used for irradiation in the reactor core. Digression from the action plan were caused by refueling and demand od the users. There have been 11 safety shutdowns, of which 6 caused by power cuts, 4 due to failure of the instruments, and 1 due to earthquake in March 1977. [Serbo-Croat] Planirani rad reaktora na nominalnoj snazi ostvaren je u iznosu od 28583 MWh. U toku 1977. godine reaktor je radio 14 dana na manjim snagama i u posebnom eksperimentalnom rezimu na zahtev korisnika. Iskoriscenost kapaciteta reaktora za ozracivanje uzoraka (na bazi neutronskog fluksa i vremena rada reaktora) bila je 41%. Ovaj izvestaj sadrzi detaljne statisticke podatke o radu i iskoriscenosti reaktora, podatke o ustedi goriva prelaskom na 80% obogaceno gorivo. Korisceno je svih 9 vertikalnih eksperimentalnih kanala u aktivnoj zoni. Uzroci odstupanja od plana rada osim zamene goriva bili su zahtevi korisnika. Bilo je 11 sigurnosnih zaustavljanja, 6 usled nestanka napona, 4 usled kvarova opreme i instrumentacije, i 1 put usled zemljotresa u martu.

  16. Nuclear Reactor RA Safety Report, Vol. 14, Safety protection measures; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 14, Sigurnosne zastitne mere

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Nuclear reactor accidents can be caused by three type of errors: failure of reactor components including (1) control and measuring instrumentation, (2) errors in operation procedure, (3) natural disasters. Safety during reactor operation are secured during its design and construction and later during operation. Both construction and administrative procedures are applied to attain safe operation. Technical safety features include fission product barriers, fuel elements cladding, primary reactor components (reactor vessel, primary cooling pipes, heat exchanger in the pump), reactor building. Safety system is the system for safe reactor shutdown and auxiliary safety system. RA reactor operating regulations and instructions are administrative acts applied to avoid possible human error caused accidents. [Serbo-Croat] Uzroci udesa na nuklearnim reaktorima mogu se svrstati u jednu od sledece tri grupe: (1) otkaz pojedinih delova opreme, ukljucujuci mernu i kontrolnu instrumentaciju, (2) greske u pogonu i eksploataciji, (3) prirodne nepogode, katastrofe. Bezbednost i sigurnost u radu nuklearnog reaktora osiguravaju se odredjenim merama koje se preduzimaju pri njegovoj izgradnji i kasnije njegovoj elsploataciji. Te mere se mogu podeliti u sledece dve kategorije: (1) mere tehnicke zastite, i (2) administrativne mere. Mere tehnicke zastite sastoje se od barijere fissionih produkata, kosuljice gorivnih elemenata, primarnog kola reaktora RA (reaktorski sud, cevovod primarnog kola, toploizmenjivac u pimpi), zgrada reaktora. Sigurnosni sistem cini sistem za sigurnosno zaustavljanje reaktora i pomocni sigurnosni sistem. Kroz odgovarajuce propise i uputstva za rad na reaktoru RA primenjene su administrativne mere neophodne za sprecavanje udes koji bi mogao nastati kao posledica ljudskog faktora.

  17. RA research nuclear reactor operation in forced regime, Annex 5; Prilog 5 - Rad istrazivackog nuklearnog reaktora RA u forsiranom rezimu, Prvo saopstenje

    Energy Technology Data Exchange (ETDEWEB)

    Mitrovic, S [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    In order to increase the flux and experimental potentials of the RA reactor, properties of the reactor operating in the forced regime have been inspected four times, twice with the spent fuel (core C), and twice with partly fresh fuel (cores E and F). Forced regime means power higher than nominal 6.5 MW. From the analyses of technology parameters during operation in the forced regime at power levels of 7 and 11 MW, state and behaviour of the components, efficiency of the biological protection and other parameters it was concluded that the reactor operation is possible at power levels of 10 MW during a whole year, and under certain conditions even longer operation at power levels up to 15 MW. This paper examines the reactor operation conditions in the forced regime and gives conclusions related to real increase of the experimental possibilities, isotope production and economic factors. Radi povecanja fluksa i eksperimentalnih mogucnosti reaktora RA, cetiri puta su proverene osobine reaktora u forsiranom rezimu, tj. na snagama vecim od nominalne (6,5 MW) i to dva puta sa istrosenim gorivom (jezgro C) i dva puta sa delimicno svezim (jezgra E i F). Iz analize tehnoloskih parametara u toku eksperimentalno rada reaktora u forsiranom rezimu na snagama od 7 do 11 MW, stanja i ponasanja opreme, efikasnosti bioloske zastite i ostalih parametara, zakljucuje se da je moguc permanentan rad reaktora tokom cele godine na snagama do 10 MW, a pod izvesnim uslovima i duzi rad na snagama do 15 MW. U radu su diskutovani uslovi rada reaktora u forsiranom rezimu i donose se zakljucci o realnom povecanju eksperimentalnih mogucnosti, proizvodnje radioizotopa i o ekonomskim faktorima (author)

  18. Experimental study of space dependent nuclear reactor kinetics - Progress report; Eksperimentalno proucavanje prostorno zavisne kinetike nuklearnih reaktora - Izvestaj o napredovanju

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D; Petrovic, M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    This paper describes experimental study of space-time behaviour of nuclear reactors by local complex-periodic perturbation of the absorption cross section and by measuring the local reactor response to this perturbation. Perturbation was done by BOR-1 fast oscillator. Cross correlation between the response and the perturbation was done numerically after completing the measurement by using digital computer. Obtained experimental results are preliminary and are measured with significant errors which were analysed in this paper. Results show qualitative agreement with those obtained by theoretical model. This paper is the first progress report in this field in our country. U radu je opisan eksperimentalni prilaz proucavanju prostorno-vremenskog ponasanja nuklearnih reaktora, vrseci lokalnu slozeno-periodicnu perturbaciju apsorpcionog preseka i mereci lokalni odziv reaktora na tu perturbaciju. Perturbacija je vrsena brzim oscilatorom BOR-1. Kroskorelacija izmedju odziva i perturbacije vrsena je numericki posle obavljenog merenja upotrebom digitalne racunske masine. Dobijeni eksperimentalni rezultati imaju preliminarni karakter i odredjeni su sa znatnim eksperimentalnim greskama koje su, u radu analizirane. Izlozeni rezultati pokazuju kvalitativna slaganja sa teorijski dobijenim modelom. Ovaj rad predstavlja prvi izvestaj o napredovanju na ovoj problematici kod nas (author)

  19. Nuclear Reactor RA Safety Report, Vol. 1, Introduction; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 1, Uvod

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Based on the agreement between governments of Socialist Federal Republic of Yugoslavia and USSR of January 28 1956, a contract was signed about construction of RA research reactor in the Boris Kidric Institute of nuclear sciences. Building of the RA reactor started in 1956, and has reached criticality in 1959. Since then it has been in almost permanent operation, except for five longer shutdown periods: in 1963 because of heavy water and primary coolant system contamination with cobalt; in 1970 because of transporting the heavy water to France for isotopic regeneration; in 1979/1980 and 1983 because of aluminium oxyhydrate deposition on the fuel element cladding in reactor active region; in 1985/1986 because of ventilation system reconstruction and construction of emergency core cooling system. RA reactor is a heavy water cooled and heavy water moderated research reactor. Since the beginning of its operation, 2% enriched metal uranium fuel was used. From 1976, 80% enriched uranium oxide fuel elements were used partially in some core regions and since 1981 the complete core was filled with this highly enriched fuel. RA reactor was designed to operate under normal conditions at 6.5 MW power and at 10 MW power under forced regime. As a powerful neutron source the reactor was meant to be used for research in the field of reactor and neutron physics, solid state physics, radiation chemistry, biology and radioactive isotopes production. RA reactor was build by Yugoslav companies based on USSR basic design project. Main components of the systems were produced in USSR. [Serbo-Croat] Na osnovu Sporazuma izmedju vlada SFRJ i SSSR od 28. januara 1956. godine, sklopljen je ugovor o izgradnji istrazivackog reaktora RA u Institutu za nuklearne nauke Boris Kidric u Vinci. Reaktor RA je poceo da se gradi 1956. godine, a kriticnost je postigao 1959. godine. Od tada je takoreci neprekidno bio u radu, izuzev u pet slucajeva duzeg stajanja: 1963. godine - zbog kontaminacije teske vode

  20. Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

    Energy Technology Data Exchange (ETDEWEB)

    Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

    1963-10-15

    entonces de comportarse como reactor de agua hirviente de ciclo directo; en cierto modo, funciona como reactor de ciclo doble y circulacion natural. (author) [Russian] 25 maya 1962 goda Argonnskaya natsional'naya laboratoriya poluchila razreshenie KAEH SSHA na ehkspluatatsiyu reaktora EBWR na moshchnosti 100 mgvt. Administrativnoe razreshenie na ehkspluatatsiyu reaktora bylo predostavleno sistemoj garantij. Mezhdunarodnogo agentstva po atomnoj ehnergii 11 iyulya 1961 goda. 15 noyabrya 1962 goda byl dostignut uroven' moshchnosti v 100 mgvt. 6 dekabrya 1962 goda ehksperimental'naya programma byla zakonchena. Odnoj iz osnovnykh tselej ee byla tshchatel'naya proverka reaktora dlya polucheniya dannykh i informatsii rabochej kharakteristiki ehtogo tipa reaktora. Ehta programma byla pervoj programmoj takogo roda i pervoj vypolnennoj programmoj. Dlya polucheniya nuzhnykh dannykh neobkhodimo bylo razrabotat' mnogie novye pribory. TSel' byla dostignuta, polucheno mnogo novykh dannykh o rabochej kharakteristike kipyashchego reaktora s estestvennoj tsirkulyatsiej. Tak,naprimer, poluchena informatsiya otnositel'no skorosti potoka tsirkulyatsii v zamknutom tsikle, predelov separatsii zhidkogo para (vydelenie para v osadok v spusknoj trube i unos zhidkosti ehflu- entom para), nedogreva, lokalizatsii dejstvitel'noj poverkhnosti razdela v reaktore i ee svyazi s urovnem vodnoj kolonki, skorosti razrusheniya para v spusknoj trube, pustotnykh koehffitsientov, reaktivnoj sposobnosti H{sub 3}BO{sub 3}, temperaturnykh koehffitsientov, ispol'zovaniya sterzhnej iz bora dlya tselej kontrolya, ispol'zovaniya svezhikh toplivnykh ehlementov, peredatochnykh funktsij,analiza shuma, nekotorykh izmerenij potoka, stabil'nosti i t.d. Krome togo, byli polucheny dannye o povedenii i tselostnosti nekotorykh reaktornykh komponentov i sistem, takikh, kak bornokislaya kontrol'naya reaktsiya, urovni radiatsii, raspredelenie produktov korrozii, vykhod iz stroya oborudovaniya, toplivo i reguliruyushchie sterzhni i t

  1. Measurement of graphite and aluminium absorption cross sections via reactor period by danger coefficient method; Merenje apsorpcionih preseka grafita i aluminijuma preko periode reaktora metodom koeficijenta opasnosti

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Markovic, V; Velickovic, Lj [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1963-07-01

    Full text: This activity is a logical continuation of the experiment at the RA reactor during 1962 which was based on compensating the effect by means of control rod. Since results are given with significant errors, new method for measuring the absorption cross sections via reactor period. Experiment was done at the RB reactor which was particularly prepared for this type of experiments. Reactor power was from 50 mW to 2 W. Absorption cross sections were measured for two types of material: domestic graphite No.3 and French graphite 'Pachiney', and two types of aluminium. Total errors in applying this method are {+-} 5%, where the source of major part of error comes from uncertainty of the standard absorption power (previous method gave {+-} 10 do 55% ). Comparison of French graphite absorption cross section obtained via reactor period and via control rod showed approximate agreement with discrepancy of 5.4% which is considered within the precision of this method. Considering the accuracy of measurement results and reactor economy it is concluded that measuring absorption cross sections of samples via period of RB reactor is more favourable than measurements by control rod at the RA reactor. Pun tekst: Ovaj rad predstavlja logican nastavak eksperimenta na reaktoru RA u toku 1962. godine, koji je bazirao na kompenzaciji efekta pomocu kontrolne sipke. Kako su rezultati dati sa velikim greskama, to se prislo novom nacinu merenja apsorpsionih preseka preko periode reaktora. Eksperiment je radjen na reaktoru RB koji je specijalno pripremljen za ovu vrstu eksperimenta. Snaga reaktora se kretala od 50 mW do 2 W. Preko periode reaktora RB odredjeni su apsorpcioni preseci za dve vrste materijala i to: domaci grafit No.3 i francuski 'Pachiney', i dve vrste aluminijuma. Ukupne greske pri ovom nacimu merenja iznose oko {+-} 5%, gde glavni deo greske nosi neodredjenost apsorpcione moci standarda (ranija metoda je dala {+-} 10 do 55% ). Poredjenjem vrednosti apsorpcionih preseka

  2. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    sushhestvovanija reaktorov nashi inzhenery i uchenye nepreryvno sovershenstvovali konstrukciju ustanovok i uluchshali metody jekspluatacii s cel'ju snizit' sebestoimost' s tem, chtoby nashi jadernye ustanovki mogli byt' konkurentosposoonymi s rabotajushhimi na iskopaemom toplive jelektrostancijami obychnogo tipa. Administrativnohozjajstvennyj uchet jadernyh materialov dolzhen byt' po mere vozmozhnosti sovremennym i jeffektivnym s tem, chtoby tehnologicheskij process, napravlennyj na snizhenie sebestoimosti, ne stradal by iz-za rastochenija jadernogo topliva i nebrezhnogo ego ucheta. Administrativno-hozjajstvennyj uchet trebuet so storony operatora jenergeticheskogo reaktora vedenija polnyh i podrobnyh uchetnyh dokumentov. Dlja udovletvorenija trebovanijam polnoty i nadezhnosti jeti dokumenty vovse ne dolzhny byt' slozhnymi. Naoborot, prostota ih javljaetsja chrezvychajno zhelatel'noj. Nesmotrja na to, chto jadernoe toplivo javljaetsja chem-to novym i sovershenno otlichnym ot topliva obychnogo tipa, nel'zja oblekat' ego pokrovom tainstvennosti. Kontrol' nalichija jadernyh materialov kak chast' administrativno-hozjajstvennogo ucheta jadernyh materialov ne ogranichivaetsja odnoj lish' rabotoj po proverke nalichija materialov, no on lezhit v osnove mnogih drugih vidov dejatel'nosti, javljajushhihsja neot{sup e}mlemoj chast'ju jekspluatacii ljubogo jenergeticheskogo reaktora, kak naprimer, otpravok obluchennogo topliva, pereobrabotki otrabotannogo topliva so svjazannoj s jetim otchetnost'ju pri regeneracii topliva i materiala, proizvedennogo pri rabote reaktora. K jetomu krugu problem otnosjatsja takzhe vyrabotka i osushhestvlenie nadlezhashhej programmy strahovanija. (author)

  3. RA reactor Action plan for 1978 - Annex VI; Prilog VI - Plan rada reaktora RA za 1978. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-12-15

    This annex include a detailed monthly action plan of the RA reactor for 1978. It was planned that the reactor will operate at nominal and lower power levels for 158 days. The plan is made with the aim to achieve same annual neutron flux as in 1977, which is somewhat higher then the annual production in the period from 1968-1975. [Serbo-Croat] Ovaj prilog sadrzi detaljan plan rada reaktora RA za 1978. godinu. Planirano je da reaktor radi na nominalnoj snazi of 6,5 MW i na manjim snagama ukupno 158 dana. Plan je napravljen tako da se ostvari godisnja proizvodnja neutronskog fluksa u obimu koji je relaizovan 1977. godine sto je nesto vise od godisnje proizvodnje u periodu 1968-1975.

  4. RA reactor operation and maintenance, Annual report 1974; Pogon i odrzavanje reaktora RA - Izvestaj o radu u 1974. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1974-12-15

    During 1974, RA reactor was operated at nominal power for 194 days and 13 days at lower power levels. The total production was 30711 MWh which is 2.4% higher than planned. Practically there were no discrepancies from the plan. The reactor was used for irradiation and experiments according to the demand of 437 users. This report contains detailed data about reactor power and experiments performed in 1974. Total number of afety shutdowns was 11, of which 8 were caused by power cuts, and 3 due to human error. Maximum individual personnel exposure dose was 50% of the maximum permissible dose. There were no accidents during this year. Decontamination of surfaces was less than during previous years. About 805 m{sup 2} of surfaces and 178 objects were decontaminated. It was concluded that the successful operation in 1974 has a special significance taking into account the financial problems. [Serbo-Croat] Reaktor RA je u 1974. godini radio na nominalnoj snazi 194 dana i 13 dana na manjim snagama. Ukupni rad iznosio je 30711 MWh odnosno 1,4% vise od planiranog. Prakticno nije bilo odstupanja od plana rada. Reaktor je koriscen za ozracivanja i eksperimente za 437 korisnika. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. U toku godine bilo je 11 sigurnosnih zaustavljanja, od cega 8 zbog elektricnog napona i 3 usled greske osoblja. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Maksimalna doza po oveku bila je 50% manja od maksimalno dozvoljene doze. Nije bilo ni jednog akcidenta. Dekontaminirano je znatno manje povrsina nego ranijih godina, i sakupljeno manje otpada nego prethodnih godina, dok tecnih efluenata nije bilo. Zakljuceno je da uspesan rad reaktora u 1974. godini ima poseban znacaj kada se imaju na umu problemi finansiranja reaktora.

  5. Nuclear Reactor RA Safety Report, Vol. 15, Analysis of significant accidents; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 15, Analiza znacajnih akcidenata

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Power excursions of the RA reactor a mathematical model of reactor kinetic behaviour was formulated to describe power and temperature coefficients for both reactor fuel and moderator. Computer code TM-1 was written for analysis of possible reactor accidents. Power excursions caused by uncontrolled control rod removal and heavy water flow into the central vertical experimental channel were analyzed. Accidents caused by fuel elements handling were discussed including possible fuel element damage. Although the probability for uncontrolled radioactive materials release into the environment is very low, this type of accidents are analyzed as well including the impact on the personnel and the environment. A separate chapter describes analysis of the loss of flow accident. Safety analysis covers the possible damage of the outer steel Ra reactor vessel and the water screens which are part of the water biological shield. [Serbo-Croat] Radi analize dinamickog ponasanja reaktora RA u toku ekskurzije snage formulisan je matematicki model koji opisuje promene snage i temperature goriva i moderatora. Za analizu predpostavljenih akcidenata realizovan je racunarski program TM-1. Analizirane su ekskurzije snage usled nekontrolisanog izvlacenja kontrolnih sipki i punjenja centralnog vertikalnog eksperimentalnog kanala teskom vodom. Analizirani su akcidenti pri rukovanju nuklearnim gorivom ukljucujuci ostecenje nuklearnog goriva. Iako je verovatnoca za nekontrolisano rasturanje radioaktivnog materijala mala, analizirani su i ovakvi moguci akcidenti koji mogu uticati kako na osoblje reaktora tako i na okolinu. Posebno poglavlje obuhvata analizu akcidenta u slucaju prestanka cirkulacije primarnog hladioca. Analiza sigurnosti reaktora obuhvata i moguce ostecenje spoljasnjeg celicnog suda reaktora RA kao i vodenih ekrana koji su deo vodenog bioloskog stita.

  6. Initial Operating Experience with the ''NPD'' Reactor; Experience recueillie pendant les premiers mois de fonctionnement du reacteur NPD; Pervyj opyt po ehkspluatatsii reaktora NPD; Experiencia inicial de funcionamiento del reactor NPD

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, L. G. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

    1963-10-15

    raboty na vysokoj moshchnosti v techenie shesti nedel' dal koehffitsient ispol'zovaniya na moshchnost', ravnyj 70% Uluchsheniya, kotorye byli dostignuty, uvelichili bezopasnost', povysili ehkspluatatsionnye kharakteristiki i prodemonstrirovali potentsial'nye metody snizheniya kapital'nykh zatrat dlya budushchikh stantsij. Tak, naprimer, v tselyakh uluchsheniya ehkspluatatsionnykh kachestv byli vidoizmeneny uplotneniya valov na nasosakh okhladitelya pervogo kontura; oborudovanie tipa kholodil'nikov, ispol'zovavsheesya dlya regeneratsii para, bylo zameneno pogloshchayushchimi kolonkami s tsel'yu umen'sheniya poteri para v tyazheloj vode. Ustanavlivayutsya takzhe ogranichiteli potoka vody v liniyakh dlya vzyatiya prob s tsel'yu umen'sheniya poteri tyazheloj vody v sluchayakh neispravnostej v soedineniyakh. V dekabre 1962 goda dve odnovremennye utechki iz mashiny, proizvodyashchej zagruzku topliva, priveli k neobychnomu obstoyatel'stvu, pri kotorom znachitel'noe kolichestvo goryachej tyazheloj vody pod vysokim davleniem popalo v kameru reaktora, gde proizoshlo neznachitel'noe umen'shenie ee izotopnoj chistoty, kotoraya zatem byla prevyshena i reaktor byl vnov' pushchen v kontse mesyatsa. Vo vremya avarii vse ustrojstva po bezopasnosti rabotali tochno i obespechili uderzhanie tyazheloj vody. (author)

  7. Results of environmental radiation monitoring and meteorology measurements (material prepared for obtaining the licence for RA reactor experimental operation); Rezultati merenja zracenja u okolini i rezultati meteoroloskih merenja (materijal pripremljen radi dobijanja dozvole za pustanje Reaktora RA u probni rad)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-10-15

    According to the demands for obtaining the licence for restarting the Ra reactor and the experimental operation this document includes the radiation monitoring measured data in the working space and environment of the RA reactor, i.e. Boris Kidric Institute. The meteorology measured data are included as well. All the measurements are performed according to the radiation protection program applied actually from the first reactor start-up at the end of 1959. [Serbo-Croat] Saglasno zahtevu za dobijanje dozvole za ponovno pustanje u probni rad reaktora RA, ovaj dokument sadrzi rezultate merenja zracenja u okolini (radnoj i zivotnoj) reaktora RA odnosno instituta 'Boris Kidric' kao i podatke o meteoroloskim merenjima. Sve merenja rade se prema programu mera zastite od zracenja koje se sprovode prakticno od prvog pustanja reaktora u rad krajem 1959. godine.

  8. RA reactor operation in 1991, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1991. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    pouzdan rad reaktora i skladu sa novim zakonskim propisima, u toku 1991. zavrseni su radovi na izgradnji sistema za udesno hladjenje, rekonstrukciju postojeceg sistema specijalne ventilacije i rekonstrukciji sistema za napajanje elektricnom energijom. Zapoceti su radovi na modernizaciji instrumentacije reaktora ali njegova realizacija u 1991. godini kasni usled zastoja u isporuci opreme iz Sovjetskog saveza. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport, ali je MAAE privremeno zabranila isporuke opreme Jugoslaviji iz politickih razloga. Kontrola i odrzavanje opreme, kao i potrebni remontni radovi izvrsavani su redovno u zavisnosti od raspolozivosti rezervnih delova. Obuka postojeceg osoblja sprovodi se redovno ali nedostatak sredstava onemogucava prijem novih radnika sto bi bilo neophodno za rad u smenama i redovno odrzavanje.

  9. RA reactor operation and maintenance in 1994, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1994. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Mikic, N; Tanaskovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1994-12-01

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. The spent fuel elements used from the very beginning of reactor operation are stored in the existing pools. Project concerned with increase of the storage space and the efficiency of handling the spent fuel elements has started in 1988 and was fulfilled in 1990. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Zavrseni su radovi na izgradnji sistema za udesno hladjenje, rekonstrukciji postojeceg sistema specijalne ventilacije i rekonstrukciji sistema za napajanje elektricnom energijom. Zapoceti su radovi na modernizaciji, odnosno zameni instrumentacije reaktora ali njegova realizacija kasni

  10. Measurements at the RA Reactor related to the VISA-2 project - Part 1, Start-up of the RA reactor and measurement of new RA reactor core parameters; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - I deo, Pustanje u rad reaktora RA i merenje fizickih parametara novog jezgra reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    The objective of the measurements was determining the neutron flux in the RA reactor core. Since the number of fuel channels is increased from 56 to 68 within the VISA-2 project, it was necessary to attain criticality of the RA reactor and measure the neutron flux properties. The 'program of RA reactor start-up' has been prepared separately and it is included in this report. Measurements were divided in two phases. First phase was measuring of the neutron flux after the criticality was achieved but at zero power. During phase two measurements were repeated at several power levels, at equilibrium xenon poisoning. This report includes experimental data of flux distributions and absolute values of the thermal and fast neutron flux in the RA reactor experimental channels and values of cadmium ratio for determining the neutron epithermal flux. Data related to calibration of regulatory rods for cold un poisoned core are included. [Serbo-Croat] Svrha merenja je odredjivanje neutronskog fluksa u reaktoru RA. S obzirom na uvecani broj tehnoloskih kanala of 56 na 68 u vezi projekta VISA-2, bilo je potrebno ponovo dovesti reaktora RA do kriticnosti i izvrsiti merenja karakteristika fluksa neutrona. Posebno je pripremljen 'program pustanja u pogon reaktora RA', koji je sadrzan u ovom dokumentu. Program merenja bio je podeljen na dve faze. Prva faza je merenje fluksa pre podizanju reaktora na nominalnu snagu. Slicna merenja vrsena su i na vecim snagama u drugoj fazi, pod uslovima ravnoteznog zatrovanja reaktora ksenonom, jer se tada pokazuju izvesne promene u odgovarajucim karakteristikama fluksa neutrona. Ovaj izvestaj sadrzi merene vrednosti raspodele fluksa i apsolutne vrednosti termalnih i brzih neutrona kao i kadmijumskih odnosa koji su korisceni za odredjivanje fluksa epitermalnih neutrona. Opisana je kalibracija regulacionih sipki za hladan nezatrovan reaktor.

  11. Research reactor RB, technical characteristics and experimental possibilities; Zbornik radova, Konferencija o koriscenju nuklearnih reaktora u Jugoslaviji

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Vranic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1978-05-15

    Nuclear research reactor RB tn the Nuclear Engineering Laboratory at the Institute of Nuclear Sciences 'Boris Kidric' in Vinca is the first reactor system built in Yugoslavia in 1958. In this report, the basic technical characteristics of this reactor are described, as well as the experimental possibilities it offers to the users. Its relatively simple construction and flexibility enables direct measurements of a series of physical parameters, and the absence of the biological protection shield makes it very useful for Various biological and other irradiations and dosimetric measurements Where strong neutron source is required. (author) Istrazivacki nuklearni reaktor RB u Laboratoriji za nuklearnu energetiku i tehnicku fiziku Instituta za nuklearne nauke 'Boris Kidric' u Vinci je prvi reaktorski sistem izgradjen u Jugooslaviji 1958. godine. U ovom radu opisane su osnovne tehnicke karakteristike tog reaktora, kao i mogucnosti za izvodjenje eksperimenata koje on pruza korisnicima. Njegova relativno jednostavna konstrukcija i fleksibilnost omogucavaju da se na njemu izvrse direktna merenja niza fizickih parametara, a s druge strane odsustvo bioloskog zastitnog omotaca cini ga veoma pogodnim za razna bioloska i druga ozracivanja, a takodje i dozimetrijska merenja gde se zahteva snazan izvor neutrona. (author)

  12. Indium-Gallium Radiation Contour of the IRT Nuclear Reactor; Circuit d'activation d'indium-gallium dans le reacteur nucleaire IRT; Indij-gallievyj radiatsionnyj kontur yadernogo reaktora IRT; Circuito de radiaciones de indio-galio del reactor IRT

    Energy Technology Data Exchange (ETDEWEB)

    Breger, A K; Ryabukin, Y S; Tulkes, S G; Volkov, E N

    1960-07-15

    -industrielles. (author) [Spanish] Basandose en un trabajo teorico ya publicado, se preparo en el reactor IRT un circuito de radiaciones de indio-galio que constituye una nueva fuente de rayos gamma de elevada intensidad. El primer circuito de este tipo ''RK-1'' se construyo para el reactor IRT en el Instituto de Fisica de la Academia de Ciencias de la Republica Socialista Sovietica de Georgia. Este trabajo estudia los puntos siguientes: calculo de la activacion de la desintegracion del conjunto indio-galio; estructura del circuito RK-1 y su disposicion en el tanque del reactor y en la camara activa; dispositivo de admision de las sustancias liquidas y gaseosas en la zona de la irradiacion; transportador de las sustancias solidas sometidas a irradiacion. En el reactor IRT, cuya potencia es de 2 000 kW, la intensidad de irradiacion del circuito es igual a la de una fuente de radiacion gamma equivalente a 20 000 g de radio. En el trabajo se estudian las posibilidades de utilizacion de este circuito con fines semi-industriales y de investigacion. (author) [Russian] Osnovyvayas' na uzhe opublikovannoj teoreticheskoj rabote, byl podgotovlen indij-gallievyj radiatsionnyj kontur yadernogo reaktora IRT, kotoryj yavlyaetsya novym moshchnym istochnikom gamma-oblucheniya . Pervyj kontur ehtogo tipa RK-1 byl podgotovlen na reaktore IRT v Institute fiziki Akademii nauk Gruzinskoj SSR. V doklade dayutsya raschety aktivizatsij dlya indij-gallievogo splava, strukturnye kompanovki RK-1 i ikh raspolozhenie v bake reaktora i goryachej kamere, ustrojstvo podachi zhidkikh i gazoobraznykh veshchestv v zonu oblucheniya i konvejer dlya tverdykh veshchestv, kotorye podlezhat oblucheniyu. V reaktore IRT moshchnost'yu 2000 kW moshchnost' oblucheniya kontura ehkvivalentna moshchnosti oblucheniya gamma-izluchatelya, obladayushchego aktivnost'yu v 20000 g ehkv. radiya. V doklade obsuzhdayutsya perspektivy ispol'zovaniya indij-gallievogo radiatsionnogo kontura dlya issledovatel'skikh i polupromyshlennykh tselej

  13. Experimental RA reactor operation with 80% enriched fuel - Program of experimental operation: a) Program of experimental operation with 80% enriched fuel at low power, b) contents of the experimental operation with 80% enriched fuel at higher power levels; Program probnog rada: a) Program probnog rada reaktora sa 80% obogacenim gorivom na malim snagama, b) sadrzaj programa probnog rada reaktora RA sa 80% obogacenim gorivom na vecim snagama

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Sotic, O; Skoric, M; Cupac, S; Bulovic, V; Maric, I; Marinkov, L [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-10-15

    Highly enriched (80%) uranium oxide fuel was regularly used in the mixed reactor core with the 2% enriched fuel since 1976. The most important changes related to reactor operation, in comparison with the original design project were related to reactor core fuelling schemes. At the end of 1979 reactor was shutdown due to the corrosion coating noticed on some fuel elements and due to decrease quality of the heavy water. Subsequently the Sanitary inspector of Serbia has prohibited further reactor operation. Restart of the reactor will not be a simple continuation of operation. It is indispensable to perform complete experimental program including measurements of critical parameters at different power levels for the core with fresh 80% enriched fuel. The aim of this document is to obtain working permission and its contents are in agreement with the procedure demanded by the Safety Committee of the Institute. It includes results of optimization and safety analysis for the initial reactor core. Since the permission for restart is not obtained, a separate RA reactor safety report is prepared in addition to the program for experimental operation. This report includes: detailed program for reactor experimental operation with 80% enriched fuel in the core at low power levels, and contents of the experimental operation with 80% enriched fuel in the core at higher power levels. [Serbo-Croat] Od decembra 1976. godine redovno je korisceno 80% obogaceno gorivo u mesanoj resetki reaktorskog jezgra sa 2% obogacenim gorivom. Najvece izmene na reaktoru u odnosu na originalni projekat izvrsene su u nacinu rukovanja gorivom. Krajem marta 1979. godine obustavljen je rad reaktora usled naslaga na gorivnim elementima i loseg stanja teske vode. Naknadno je izdata zabrana za rad reaktora od strane Sanitarnog inspektora SR Srbije. Ponovno pustanje reaktora u rad nece biti jednostavan nastavak rada. Neophodno je da se izvede kompletan program merenja kriticnih parametara i drugih

  14. Operation, maintenance and utilization of the RA reactor, Annual report for 1980; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1980. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-12-15

    During 1980 the activities of RA reactor staff was conducted in two directions: repair works and determination of the state of the existing equipment; and preparing and constructing additional equipment and completing the documentation needed to fulfill the new legal regulations. preparation of the existing equipment for future operation was finished, but construction of the additional equipment (according to the regulations) is not done at planned rate due to different reasons such as lack of budget, administration, import. This report includes a chapter devoted to the analysis of the operation difficulties that caused prohibition of reactor operation as well as difficulties in achievement of the planned activities for 1980. Data about financial issues are included as well. [Serbo-Croat] U toku 1980. godine rad OOUR-a Nuklearni reaktor RA odvijao se u dva smera: remontnim radovima i utvrdjivanju stanja postojece opreme i u pripremi i ugradnji potrebne dodatne opreme i kompletiranju neophodne dokumentacije prema novim zakonskim propisima. Priprema postojece opreme za rad je u potpunosti izvrsena, dok se projekti i ugradnja dodatne opreme (prema zakonskim obavezama) ne odvija potrebnom brzinom zbog raznih objektivnih razloga, kao nedostatak sredstava, odobrenja, uvoza. Ovaj izvestaj sadrzi poglavlje posveceno analizi teskoca u radu koje su dovele do zabrane rada reaktora, i teskoca u realizovanju plana rada u 1980. godini, ako i podatke o finansiranju projekta 'pogon, odrzavanje i eksploatacija reaktora RA'.

  15. Nuclear Reactor RA Safety Report, Vol. 16, Maximum hypothetical accident; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 16, Maksimalni hipoteticki akcident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-15

    Fault tree analysis of the maximum hypothetical accident covers the basic elements: accident initiation, phase development phases - scheme of possible accident flow. Cause of the accident initiation is the break of primary cooling pipe, heavy water system. Loss of primary coolant causes loss of pressure in the primary circuit at the coolant input in the reactor vessel. This initiates safety protection system which should automatically shutdown the reactor. Separate chapters are devoted to: after-heat removal, coolant and moderator loss; accident effects on the reactor core, effects in the reactor building, and release of radioactive wastes. [Serbo-Croat] Sema granjanja za maksimalni hipoteticki akcident obuhvata osnovne elemente: pocetak akcidenta, faze razvoja akcidenta i stablo razvoja - sema potencijalnih akcidentnih tokova. Uzrok pocetka akcidenta je pucanje cevovoda primarnog rashladnog sistema jezgra, sistema teske vode. Gubitak primarnog hladioca izaziva pad pritiska u primarnom sistemu hladjenja na ulazu u reaktorski sud. Ovaj poremecaj pobudjuje sigurnosno kolo zastite koje automatski treba da prekine rad reaktora. Posebno je razmatrano generisanje zaostale snage, isticanje hladioca i moderatora, efekti akcidenta na jezgro, efekti u zgradi reaktora, oslobadjanje radioaktivnih produkata.

  16. Association of Average Telomere Length with Body-Mass Index and Vitamin D Status in Juvenile Population with Type 1 Diabetes / Povezava Povprečnih Dolžin Telomerov Z Indeksom Telesne Teže in Vitaminom D Pri Mladostnikih S Sladkorno Boleznijo Tipa 1

    Directory of Open Access Journals (Sweden)

    Tesovnik Tine

    2015-03-01

    Full Text Available Izhodišče. Sladkorna bolezen tipa 1 (SBT1 je kronična avtoimunska bolezen, pri kateri hiperglikemija ter zvišana raven oksidativnega stresa in končnih produktov glikacije skupaj z genetskimi in okoljskimi dejavniki privedeta do nastanka diabetičnih zapletov. Krajše dolžine telomerov so povezane s hiperglikemičnimi epizodami in nižjimi serumskimi vrednostmi vitamina D.

  17. Operation and maintenance of the RA reactor, RA Research reactor. Annual report 1976; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1976. godini

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    remonta do kojih je dolazilo zbog kvarova (nastalih zbog neizvrsavanja investicionog odrzavanja u toku poslednjih 6 godina) zatim nemogucnost ranijeg pocetka koriscenja novog goriva u reaktoru RA i istrosenosti rezervi starog 2% obogacenog goriva i na kraju zbog obimnog programa eksperimenata u oblasti sigurnosnih analiza vezanih za uvodjenje novog visokoobogacenog goriva u reaktor RA. Na reaktoru RA uspesno su izvrseni eksperimentalni i teorijski radovi u oblasti sigurnosnih analiza za prevodjenje reaktora RA na novo 80% obogaceno gorivo, krunisani eksperimentalnom kampanjom reaktora RA u decembru 1976, kojom se zavrsava 17-to godisnji period koriscenja 2% obogacenog goriva i otpocinje period koriscenja novog 80% obogacenog goriva u reaktoru RA. Ovaj uspeh je od izuzetnog znacaja za reaktor RA i njegove korisnike, jer ce rezultovati u povecanju osnovne proizvodnje neutronskog fluksa od 50%, pri porastu cene kostanja rada reaktora od oko 4%. Podnet je zahtev za konacno odobrenje prelaznog rezima za uvodjenje ovog goriva, kojim se postize usteda od najmanje 2 200 000 dinara. Ovim se obezbedjuje da u 1977. godini i dalje, rad reaktora ne bude vise ometan ''kriticnim'' ili drugim eksperimentima u vezi sa uvodjenjem novog goriva u reaktor. Izvrsen je obiman program remontnih i drugih radova veoma akutne prirode, koji takodje omogucuju nesmetan rad u 1977. godini. Neki od ovih radova nisu radjeni nikad ranije, a drugi nisu radjeni u proteklih 6 godina. Najzacajniji zahvati ove vrste bili su: nabavka Al-cevi od specijalne legure, izrada i montiranje tehnoloskoh kanala; obimno ispitivanje uzroka curenja spoljasnjeg suda; remont teskovodne pumpe; zamena dva vertikalna tehnoloska kanala. Nabavljena je osnovna oprema za izgradnju sistema za hladjenje u slucaju udesa. Izvrseno je opremanje vrucih komora reaktora RA.

  18. Ra reactor operation plan for 1976 - Annex 6; Prilog 6 - Plan rada reaktora RA za 1976. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    Contrary to previous years the RA reactor operation plan for 1976 is conditioned by more uncertainties than ever for the following reasons. It is planned for February to repair the components in order to eliminate the consequences of leaking from the vertical experimental channel VK-4 which happened in december 1975. Apart from this, measurements related to transfer of the core to highly enriched fuel under minimum power are foreseen to be performed in February. In April, it would be indispensable to locate the point of He gas leaking and its prevention. Core transfer to highly enriched fuel is planned for April for testing of the fuel elements under operating conditions and step by step increase of the power density up to the nominal power. Complete plan for core transfer would be available by the end of February 1976. It is planned to make-up for the mentioned delays from May-December 1976. [Serbo-Croat] Za razliku od prethodnih godina izrada plana rada reaktora RA za 1976. godinu vezana je za mnogo vise neizvesnosti nego ikada ranije iz sledecih razloga. U februaru se vrsi remont opreme i uklanjanja posledica procurivanja vertikalnog eksperimentalog kanala VK-4, koje se dogodilo decembra 1975. Sem toga u februaru se vrse merenja na minimalnim snagama u sklopu priprema za prelazak na novo gorivo. U aprilu ce biti neophodno lociranje mesta gde istice He gas kao i otklanjanje uzroka ovog curenja. Planirano je da se u aprilu ubaci novo gorivo u jezgro u cilju testiranja pod radnim uslovima uz postepeno povecanje snage do nominalne. Planirano je da se smanjeni obim rada usled navedenih uslova nadoknadi u potpunosti u periodu maj-decembar 1976.

  19. Detection of tritium in the air surrounding the heavy water reactors; Elementi detekcije tricijuma u vazduhu kod teskovodnih nuklearnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Matic-Vukmirovic, Z; Hadzisehovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1967-03-15

    This paper contains the study of the literature concerned with physical properties of the tritium, problems of detection control of the tritium level in the atmosphere in the vicinity of heavy water reactors. It is stated that a complete and efficient control of tritium activity, from radiation protection point of view can be achieved only by simultaneous triple measurements: direct measurement of tritium in the air by stationary or movable instruments; air sampling and measurement of activity by laboratory instrumentation; and measurement of tritium in the bio-material of the personnel who have inhaled air contaminated with tritium. Laboratory equipment was adapted for tritium detection in air samples. A method for measuring the specific tritium activity was developed and implemented. The tritium level and distribution in the air were measured during exchange of the fuel channel in the RA reactor. The obtained results indicate that tritium could be dangerous for the staff involved. Proucena je literatura u kojoj se tretiraju osnovne fizicke karakteristike tricijuma, kao i problemi detekcije i kontrole u vazduhu kod teskovodnih nuklearnih reaktora. Utvrdjeno je da kompletna i efikasna kontrola aktivnosti tricijuma, sa aspekta zastite od zracenja, moze biti ostvarena samo ako se vrse istovremeno trostruka merenja: merenje aktivnosti tricijuma u vazduhu direktno, prenosnim ili stacioniranim instrumentima; uzimanje uzoraka vazduha i merenje aktivnosti na laboratorijskoj aparaturi; i merenje aktivnosti tricijuma u biomaterijalu osoblja koje je udisalo vazduh kontaminiran tricijumom. Izvrsena je adaptacija laboratorijske aparature za potrebe detekcije tricijuma u uzorcima vazduha. Razradjen je i uhodan postupak merenja koncentracije aktivnosti tricijuma u uzorcima vazduha. Izvrsena su merenja i dobijeni su rezultati o nivou i raspodeli tricijuma u vazduhu pri operaciji zamene kanala sa gorivom na reaktoru RA u Vinci. Dobijeni rezultati ukazuju na opasnost koju po radno

  20. Determination of reactor parameters in a simulated RA reactor lattice by measuring the reactivity level of heavy water in D{sub 2}O moderated RB reactor; Odredjivanje reaktorskih parametara u simuliranoj resetki reaktora RA merenjem reaktivnosti nivoa teske vode u D{sub 2}O moderiranom reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

    Takac, S M; Markovic, H D; Dimitrijevic, Z B [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1974-07-01

    Direct method for experimental determination of the neutron age {tau} in the reactor lattice is not developed. Fermi theory for determining {tau} by measuring the reactivity level of the heavy water can be applied for a limited number of reactor lattices. An attempt was made to apply this approach for a complex reactor core with side and upper reflector. As expected the obtained results were not satisfactory, and {tau} was determined by Dessauer formula which gives more realistic estimation of thermalization in the reactor cell. major discrepancies are resulting from the fact that the lower reflector was neglected. But it is possible to to determine {tau} for reactor core with reflectors by additional measurements of axial distribution and other experimental data for {tau}. This is quite tedious numerical procedure. Obtained experimental data for a number of reactor parameters are compared to the initial data of the RA reactor core showing very good agreement. [Serbo-Croat] Ekspeimentalna metoda za direktno odredjivanje starosti neutrona {tau}, u resetki reaktora do danas nije razvijena. Primenjena Fermijeova teorija za odredjivanje {tau} preko merenja reaktivnosti nivoa teske vode, ocigledno se moze koristiti samo na ogranicen spektar reaktorskih resetki. U ovom radu pokusano je da se vidi primenljivost iste u slozenom - bocno i odozdo - reflektovanom jezgru reaktora. Naravno dobijeni rezultati nisu zadovoljili, sto se i moglo ocekivati, pa je {tau} odredjen preko Dessauer-ove formule, sto daje daleko blizu sliku stvarnog stanja procesa termalizacije u celiji reaktora. Ocigledno vece neslaganje primenjene teorije dolazi od zanemarivanja donjeg reflektora u jezgru reaktora. Medjutim, dopnskim merenjem aksijalne raspodele i na osnovu ostalih eksperimentalnih podataka za {tau}, moguce je odrediti eksperimentalno reflektorski koeficijent za visestruko reflektovano jezgro reaktora, sto numericki predstavlja mukotrpan i dugotrajan rad na racunaru. Dobijeni

  1. Type 1 Diabetes in the Young: Organization of two National Centers in Israel and Slovenia / Sladkorna Bolezen Tipa 1 Pri Otrocih in Mladostnikih: Organizacija Dela V Dveh Nacionalnih Centrih V Izraelu in Sloveniji

    Directory of Open Access Journals (Sweden)

    Bratina Nataša

    2015-03-01

    Full Text Available Sladkorna bolezen tipa 1 je kronično avtoimuno obolenje, ki najpogosteje prizadene mlade ljudi. Incidenca bolezni zadnjih 50 let narašča po vsem svetu, v povprečju je letni porast incidence ocenjen na 4 %, ob tem pa starost bolnikov ob času diagnoze pada. Raziskave kažejo, da je dobra presnovna urejenost bolnikov s sladkorno boleznijo zelo pomembna, saj je s tem mogoče odložiti pozne zaplete bolezni ter izboljšati kvaliteto življenja bolnikov in njihovih družin. Neprekinjena edukacija bolnikov skupaj z možnostmi moderne tehnologije lahko prispeva k izboljšanju njihove presnovne urejenosti. Presnovno urejenost spremljamo z določanjem glikoziliranega hemoglobina (HbA1c ter s številom težkih hipoglikemij in ketoacidoz na populacijo pacientov v določenem časovnem obdobju. V prispevku sta opisana dva nacionalna referenčna centra za obravnavo otrok, mladostnikov in mladih odraslih s sladkorno boleznijo v Izraelu in Sloveniji.

  2. RA reactor operation and maintenance in 1989, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1989. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    , koja je zavrsena 1989, i izradu uredjaja za rukovanje ozracenim gorivom, koji je u fazi montiranja. Planirano je da ovi poslovi budu zavrseni do sredine 1990. godine. Obuka postojeceg osoblja sprovodi se redovno ali novoprimljeni radnici obuceni za rad u pogonu nisu mogli da steknu potrebno sikustvo posto reaktor nije bio u pogonu od 1984. Nedostatak sredstava onemogucava prijem novih radnika i utice na celokupni status i aktivnosti vezane za rekonsrukciju i modernizaciju reaktora RA.

  3. Dosimetry and radiation protection at the RA reactor in 1972; Dozimetrija i zastita kod reaktora RA u 1972. godini

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1973-07-01

    Dosimetry results collected within radiation protection of the RA reactor during this year are presented. Neutron and gamma radiation data were measured at characteristic control points. Statistical review of the total number of measurement is given as well. The report includes contents of radioactive gasses and aerosols in the air, as well as the contamination data of surfaces, clothes and uncovered body parts of the personnel. Particular accident which occurred during dismantling of the experimental channel containing the capsule with the new fuel element was analysed. This accident occurred at the RA reactor at the beginning of this year. It was found that that the maximum individual external dose was 2.2 R, and that only one individual was exposed to this dose. About 15% of the personnel was exposed to doses between 1 and 2 R, the remaining 85% was exposed to doses less than 1 R. Base on the frequency of activities undertaken in the contaminated regions, safety and control measures and expected internal exposure of the personnel, it was evaluated that the internal exposure could be neglected compared to the external exposure of the personnel. Prikazani su rezultati sakupljani u toku godine u okviru dozimetrijske kontrole i zastite kod reaktora. Dati su podaci o nivoima neutrona i gama zracenja na karakteristicnim kontrolnim mestima, kao i statisticki pregledi ukupnog broja merenja. Navedeni su rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela radnog osoblja. Analiziran je specifican akcident koji se odigrao na reaktoru pocetkom godine, pri demontazi eksperimentalnog kanala sa kapsulom novog gorivog elementa. Na kraju, izlozena je analiza ozracivanja radnog osoblja. Konstatovano je da je maksimalna individualna doza spoljasnjeg ozracivanja bila 2,2 (R), i da je ovoj dozi bilo izlozeno samo jedno lice. Oko 15% osoblja bilo je izlozeno dozama izmedju 1 i 2 (R), a ostalih 85

  4. Independent CO{sub 2} loop for cooling the samples irradiated in vertical experimental channels of the RA reactor, Vol. I; Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA, Album I

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Pavlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-06-15

    Project 'independent CO{sub 2} loop for cooling the samples irradiated in the vertical experimental channels of the RA reactor' is presented in two volumes: volume I - head of the low temperature coolant loop for reactor RA, and volume II - Outer low-temperature reactor coolant loop. Volume I includes: the design specifications for the head of the low-temperature coolant loop, technical description, thermal calculation, calculations of mechanical loads, antireactivity and activation of the components of the coolant loop head, engineering schemes and drawings, cost estimation data. [Serbo-Croat] Projekat 'Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA', sastoji se od dva albuma: album I - Glava niskotemperaturno rashladne petlje za reaktor RA, album II - Spoljno kolo niskotemperaturne rashladne petlje za reaktora. Album I sadrzi projektni zadatak glave niskotemperaturne petlje, tehnicki opis, termicki proracun, proracun mehanickih naprezanja, antireaktivnosti i aktivacije kontrukcionih elemenata glave petlje, konstrukcione seme i crteze glave petlje, predracun.

  5. RA reactor operation and maintenance in 1990 with comparative evaluation from 1986-1990, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1990. godini, uz uporedni pregled za period 1986-1990. godina

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Vasovic, B; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1990-12-15

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The new emergency cooling system and the reconstruction of the existing ventilation system were finished in 1989, the conditions for further reactor operation were fulfilled. In the meantime new licensing regulations adopted in 1988 were not demanding the mentioned conditions for reactors operated at power less than 10MW, RA reactor power being 6.5 MW. But the reactor could not be restarted due to planned renewal of the reactor instrumentation. It is planned to exchange the complete instrumentation by the end of 1991. Training program for the staff operating and maintaining the reactor components was prepared in 1985. Reconstruction, modification and construction of components demanded new documentation needed for further safe reactor operation. New version of RA reactor safety report was finished in 1986 according to the recommendations of IAEA and licensing regulations of Yugoslavia. In 1989, new documents were written covering regulations and instructions for reactor operation. The new reactor experimental loop was designed in 1986, and constructed and tested in 1990. All the reactor components were maintained by specific reactor services. Financing of the reactor remains a permanent problem. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula 1984. godine Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Radovi na izgradnji sistema za udesno hladjenje i rekonstrukciji postojeceg sistema specijalne ventilacije zavrseni su 1989. godine. Uslovi za nastavak rada reaktora

  6. Activity of the RA Reactor Physics group in 1980 - Definition of the Operation conditions for future safe and economical RA reactor operation with 80% enriched fuel; Prilog Ia - Rad sluzbe za fiziku reaktora RA u 1980. godini - Definisanje pogonskih uslova za dalji siguran i ekonomican rad reaktora RA sa 80% obogacenim gorivom

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-12-15

    During 1980. the RA reactor was not in operation. That is why this period was devoted to definition of operating conditions for further reactor operation with 80% enriched fuel. The fuel elements which were in the core at the moment of shutdown in March 1979will not be used again (388 80% enriched fuel elements, and 511 2% enriched fuel elements). The reactor will be operated only with 80% enriched fuel, staring with initiat core configuration with 440 elements on the borders gradually changing to equi;librium core with 720 fuel elements. The analyses were concerned with safety issues of future operation. [Serbo-Croat] Reaktor RA tokom 1980 godine nije radio. Zbog toga je ovaj period iskoriscen za intenzivan rad na definisanju pogonskih uslova za dalji rad reaktora sa 80% obogacenim gorivom. Gorivo sa kojim je reaktor prestao da radi marta 1979. godine (388 gorivnih elemenata 80% obogacenoh i 511 elementa 2% obogaceno) nece biti vraceno u jezgro, vec ce reaktor raditi samo sa 80% obogacenim gorivom, pocev od konfiguracije sa 440 elemenata na periferiji do ravnotezne konfiguracije sa 720 elemenata. Sve nalize su se bavile sigurnosnim aspektima rada reaktora sa visokoobogacenim gorivom u jezgru.

  7. Operation, maintenance and utilization of the RA reactor - Report on operation in 1979; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1979. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M

    1979-12-15

    During 1979 the RA reactor was in operation only three months, i.e. only 24% of the planned activity was achieved. The reactor operation was interrupted in March due to problems that could not be solved by the existing equipment. Alkalinity of the heavy water resulting from the existing ammonia ions could not be removed by the existing distillation system. In addition deposition of aluminium oxyhydrate on the fuel elements was increased. This was noticed during routine control when the reactor was shutdown for refueling. The decision of the Director general of the Institute and sanitary Inspector followed, prohibiting further reactor operation. A separate chapter of this report is devoted to the analysis of the difficulties and possible solution of the problem in cooperation with the experts from different laboratories of the Institute. Aged and damaged instruments at the reactor were not exchange due to lack of budget. During the operation there were no accidents. [Serbo-Croat] U toku 1979. godine plan rada ostvaren je sa 24%, odnosno reaktor je radio samo prva tri meseca. U martu je doslo do prekida rada reaktora zbog pojave koja se nije mogla otkloniti postojecom opremom. Alkalnost teske vode, posledica prisustva amonijum jona, ne moze se odstraniti sistemom destilacije. Pored toga usled dotrajalosti opreme povecano je talozenje aluminijum oksihidroksida na gorivnim elementima. Ova pojava uocena je tokom rutinske kontrole prilikom izmene goriva a usledila je obustava rada resenjem Direktora i sanitarnog inspektora. Posebno poglavlje ovog izvestaja posveceno je analizi teskoca u radu i reaktora i resavanju nastalih problema sa gorivom u saradnji sa saradnicima drugih laboratorija Instituta. Dotrajali uredjaji i oprema nisu zamenjeni usled nedostatka sredstava. U toku rada nije bilo akcidenata.

  8. RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1986; Istrazivacki nuklearni reaktor RA, deo 1, pogon i odrzavanje nukleanog reaktora RA u 1986. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    In order to enable future reliable operation of the RA reactor, according to new licensing regulations, three major tasks started in 1984 were fulfilled: building of the new emergency system, reconstruction of the existing ventilation system, and reconstruction of the power supply system. Simultaneously in 1985/1986 renewal of the instrumentation and reconstruction of the system for handling and storage of the spent fuel in the reactor building have started. Design projects for these tasks are almost finished and the reconstruction of both systems is expected to be finished until 1988 and mid 1989 respectively. RA reactor Safety report was finished according to the recommendations of the IAEA. Investments in 1986 were used for 8000 kg of heavy water, maintenance of reactor systems and supply of new components, reconstruction of reactor systems. This report includes 8 annexes concerning reactor operation, activities of services and financial issues. [Serbo-Croat] Sa ciljem da se obezbedi pouzdan rad reaktora RA a u skladu sa zakonskim propisima, zavrsena su tri velika zahvata zapoceta 1984: izgradnja novog sistema za udesno hladjenje, rekonstrukcija postojeceg sistema za ventilaciju, i modernizacija reaktorske instrumentacije. Istovremeno tokom 1985/1986. zapoceta je modernizacija instrumentacije i rekonstrukcija sistema za rukovanje i skladistenje iskoriscenog goriva u zgradi reaktora. Projekti za navedene radove su vec zavrseni ili su u zavrsnoj fazi, a ocekuje se da ce rekonstrukcija oba sistema biti zavrsena do kraja 1988. odnosno sredine 1989. godine. Izrada izvestaja o sigurnosti reaktora RA, prema preporukama MAAE zavrsena je 1986. Investiciona ulaganja na reaktoru Ra u 1986. iskoriscena su za: nabavku 8000 kg teske vode, za investiciono odrzavanje reaktorskih sistema i nabavku opreme, za rekonstrukciju reaktorskih sistema. Ovaj izvestaj sadrzi 8 priloga koji opisuju rad reaktora, rad strucnih sluzbi i finansiranje.

  9. The training of the staff for work with radioactive materials and work on nuclear reactor in the Institute; Obuka kadrova za rukovanje radioizotopima i pogon nuklearnih reaktora u Institutu 'Boris Kidric' - Vinca

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M; Mladjenovic, O; Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1978-05-15

    A short informational review of the activities in the 'Boris Kidric' Institute on the training courses for the use of radioactive materials and for operating nuclear reactors including power reactors. The survey of the courses is given in the enclosures. (author) Kratak informativni pregled delatnosti u IBK na kursevima za obuku kadrova u rukovanju readioaktivnim materijalima i pogonu nuklearnih reaktora, ukljucujuci reaktore snage. pregled kurseva i materijala za njih dati su u prilozima. (author)

  10. Activity of the Service for maintenance of mechanical equipment of the RA reactor - Report, Annex II; Prilog II - Rad sluzbe za odrzavanje masinske opreme reaktora RA u 1979. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1979-12-15

    Service for mechanical components at the RA reactor includes: control and maintenance of utility components, mechanical workshop, hot cells and storage. Control and maintenance of main components covers: reactor core, heavy water system, technical water system, gas system. This service is responsible for the following auxiliary systems: transportation units; spent fuel storage pool; special ventilation system; personal protection appliances; hot cells. Maintenance of the reactor building, ventilation, heating, water supply, sewage, fire protection devices, gas and compressed air systems are included. [Serbo-Croat] Sluzba za masinsku opremu nuklearnog reaktora RA obuhvata: kontrolu i odrzavanje masinske opreme postrojenja, masinsku radionicu, vruce komore i prirucni magacin. Kontrola i odrzavanje osnovnih sistema obuhvata centralno telo reaktora, sistem teske vode, sistem tehnicke vode, gasni sistem. Pomocni sistemi koji spadaju u delatnost ove sluzbe su: transportna oprema, bazen za odlezavanje ozracenog goriva, sistem specijalne ventilacije, licna zastitna sredstva, vruce komore. Odrzavanje zgrade reaktora, ventilacije i grejanja, vodovoda i kanalizacije, opreme za protivpozarnu zastitu, instalacije gasa i komprimovanog vazduha su takode zadatak ove Sluzbe.

  11. Activity of the Service for maintenance of mechanical structures of the RA reactor - Report for 1980, Annex II; Prilog II - Rad sluzbe za odrzavanje masinske opreme reaktora RA - Izvestaj za 1980. god

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-12-15

    Service for mechanical components at the RA reactor includes: control and maintenance of utility components, mechanical workshop, hot cells and storage. Control and maintenance of main components covers: reactor core, heavy water system, technical water system, gas system. This service is responsible for the following auxiliary systems: transportation units; spent fuel storage pool; special ventilation system; personal protection appliances; hot cells. Maintenance of the reactor building, ventilation, heating, water supply, sewage, fire protection devices, gas and compressed air systems are included. [Serbo-Croat] Sluzba za masinsku opremu nuklearnog reaktora RA obuhvata: kontrolu i odrzavanje masinske opreme postrojenja, masinsku radionicu, vruce komore i prirucni magacin. Kontrola i odrzavanje osnovnih sistema obuhvata centralno telo reaktora, sistem teske vode, sistem tehnicke vode, gasni sistem. Pomocni sistemi koji spadaju u delatnost ove sluzbe su: transportna oprema, bazen za odlezavanje ozracenog goriva, sistem specijalne ventilacije, licna zastitna sredstva, vruce komore. Odrzavanje zgrade reaktora, ventilacije i grejanja, vodovoda i kanalizacije, opreme za protivpozarnu zastitu, instalacije gasa i komprimovanog vazduha su takode zadatak ove Sluzbe.

  12. Operation and maintenance of the RA Reactor in 1985, Part 1, Annex B - Report of the Technology Service; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1985. godini - Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Vukadin, Z; Stosic, O; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-12-01

    Technology service is established according to the need of unified technology control of the reactor, based on the organizational structure developed in USA, a part of which was applied at the Krsko NPP. Tasks of this service are: regular control and recording of operating reactor parameters under steady state and accidental conditions; control of chemical state of the reactor core (control of Ph values and electro conductivity of the heavy water and technical water); dosimetry parameters control and recording; safety and optimisation analyses when planning reactor core modifications; (changing the type of fuel, design of new components); cooperation with the reactor users during isotope production, activation analyses, application of neutron beams; participating in research programs; planning refueling. The most important task performed by this service was conversion of the core from 2% to 80% enriched fuel elements. A methodology for optimizing the reactor application was developed. Operation of the heavy water purification system, heavy water parameters, and operation of the gas system were controlled. Radiation and contamination levels in the working environment were measured, individual and collective doses. [Serbo-Croat] Tehnoloska sluzba uspostavljena je u skladu sa ispoljenim potrebama jedinstvene tehnoloske kontrole reaktora, oslanjajajucui se na organizacionu semu koja je razvijena u SAD, a cija je jedna varijanta primenjena na NE Krsko. Zadaci sluzbe su obavljanje sledecih zadataka: redovna kontrola i evidencija radnih parametara reaktora u redovnim i akcidentalnim uslovima; kontrola hemijskog rezima u reaktoru (kontrola PH vrednosti i elektroprovodnosti teske i tehnicke vode); kontrola i evidencija tehnicke dozimetrije; sigurnosne i optimizacione analize prilikom planiranja izmena na reaktoru (promene vrste goriva, izgradnja novih elemenata opreme); saradnja sa korisnicima reaktora prilikom prozivodnje izotopa, aktivacione analize, koriscenja

  13. Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Task 2.50.05; Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA, Zad. 2.50.05

    Energy Technology Data Exchange (ETDEWEB)

    Stojic, M; Pavicevic, M

    1964-07-01

    This report contains the following volumes V and VI of the Project 'Independent CO{sub 2} loop for cooling the samples irradiated in RA reactor vertical experimental channels': Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, and Safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels. Ovaj izvestaj sadrzi dva albuma zadatka 'Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA', Zad. 2.50.05: Album V: Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA i Album VI: Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA.

  14. Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia; Dvadeset godina hemije vezane za potrebe i koriscenje nuklearnih reaktora u Institutu za nuklearne nauke 'Boris kidric' i Vinci

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-07-01

    This publication covers nine review papers on the following topics related to the needs and utilization of nuclear reactors in the Boris Kidric Institute of nuclear sciences during previous twenty years: radiochemistry, hot atom chemistry, isotope production, spent nuclear fuel reprocessing, chemistry of transuranium elements; liquid radioactive waste processing, purification of reactor coolant water by inorganic ion exchangers, research related to deuterium concentration processes, and chemical dosimetry at the RA reactor. [Serbo-Croat] Ova publikacija obuhvata devet radova, po sledecim naslovima, a odnose se na potrebe i uslove nuklearnih reaktora u Institutu za nuklearne nauke 'Boris Kidric' tokom prethodnih dvadeset godina: radiohemija, hemija vruceg atoma, proizvodnja radioaktivnih izotopa, prerada isluzenog nuklearnog goriva, hemija transuranskih elemenata, obrada radioaktivnih otpadnih voda, preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca, istrazivanje procesa za koncentrovanje deuterijuma i hemijska dozimetrija reaktora RA.

  15. Data about operation and utilization of the RA in 1976 - Report, Annex I; Prilog I - Podaci o radu i iskoriscenosti reaktora RA u 1976. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    , nemogucnost da se predvidi tacno vreme za eksperimente u okviru (uspesno provedenog) programa prevodjenja reaktora RA na novo visokoobogaceno gorivo, posto neki od ovih eksperimenata takodje nikada ranije nije radjen. Sem toga bilo je i nepredvidjenih vecih remontnih radova zbog nepredvidjenih kvarova. Planirano je 6 izmena goriva koje su ostvarene sa zakasnjenjem. Podaci o planiranom i ostvarenom radu reaktora u 1976. godini prikazani su u ovom izvestaju kao i podaci o prekidu rada. Kracih prekida i sigurnosnih zaustavljanja je bilo 12 u ukupnom trajanju od 64 casa. Reaktor je radio na nominalnoj snazi od 6.5 MW. Akcidenata vecih razmera nije bilo, medjutim dva slucaja mogu se opisati kao akcidentalne situacije po nacinu kako su nastali. Prvi je prskanje cevi kod lezaja teskovodne pumpe a drugi kontaminacija hale i hodnika nastala prilikom pripreme masine za izmenu goriva (izlivanje teske vode). Ovaj prilog sadrzi i podatke o koriscenju eksperimentalnog prostora i iskoriscenosti reaktora.

  16. Radiation protection at the RA Reactor in 1989, Part -2, Decontamination, collection of treatment of fluid and solid radioactive waste, Annex 3; Deo 2 - Zastita od zracenja kod reaktora RA u 1989. godini, Dekontaminacija i intervencija, sakupljanje i obrada tecnih i cvrstih radioaktivnih otpadnih materija za potrebe reaktora RA - Prilog 3

    Energy Technology Data Exchange (ETDEWEB)

    Mandic, M; Vukovic, Z; Plecas, I; Knezevic, Lj; Lazic, S; Bacic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [Serbo-Croat] Tokom rada reaktora RA dolazi do stvaranja odredjenih cvrstih otpadnih materijala cija prosecna kolicina zavisi od vremena rada reaktora i aktivnosti koje se tamo obavljaju. Tokom remonta, kada reaktor ne radi kao i pri akcidentalnim situacijama nastaju vece kolicine otpadnih materijala koje zavise od obima i vrste remontnih operacija i obima dekontaminacije kontaminirane radne povrsine i kontaminiranog alata, predmeta, opreme, itd. Nastali otpadni materijali se razvrstavaju i pakuju na mestu nastanka prema odgovarajucim propisima u skladu sa principima zastite od zracenja i aspekta bezbednosti u cilju minimiziranja nepotrebnog ozracivanja ljudstva za preuzimanje, kontrolu, transport, naknadnu obradu RAO i dekontaminaciju. Pri nerutinskim operacijama (dekontaminacija, remont, kontaminiarni otpadni materijal velike zapremine i sl.), strucna sluzba Institita ZASTITA pruza strucne konsultacije i pomaze pri planiranju

  17. Operating Experience with the BR-5 Reactor; Experience acquise aupres du reacteur BR-5; Opyt ehkspluatatsii reaktora BR-5; Experiencia practica con el reactor BR-5

    Energy Technology Data Exchange (ETDEWEB)

    Lejpunskij, A. I.; Kazachkovskij, O. D.; Pinkhasik, M. S.; Aristarkhov, N. N.; Karpov, A. V.; Larin, E. P.; Efimov, I. A.

    1963-10-15

    remontnykh rabot na radioaktivnom zhidkometallicheskom konture reaktora na bystrykh nejtronakh BR-5. Osveshchayutsya voprosy ehkspluatatsii reaktora posle dostizheniya proektnogo 2%-nogo vygoraniya topliva pri nalichii nekotorogo narusheniya plotnosti otdel'nykh teplovydelyaptsikh ehlementov. Provoditsya opyt po razgruzke aktivnoj zony, issledovaniyu sostoyaniya i germetichnosti teplovydelyaptsikh ehlementov, dezaktivatsii oborudovaniya i truboprovodov I radioaktivnogo kontura posle dostizheniya 5% vygoraniya topliva. (author)

  18. Reactor utilization; Eksploatacija reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel.

  19. Data concerning operation and application of RA reactor in 1975, Annex 1; Prilog 1 - Podaci o radu i iskoriscenosti reaktora RA u 1975. godini

    Energy Technology Data Exchange (ETDEWEB)

    Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    RA reactor was operating according to the plan for 1975 adopted in December of the previous year. It was planned for reactor to be operated at nominal power first 10-20 days each month, three following days were reserved for different power levels according to the users' demand. Four fuel exchanges were planned and fulfilled with minor delay. Data concerning planned and real operation, as well as delays from the plan and shorter interruptions are presented in tables of this Annex. It is shown that all the delays and interruptions which amounted to 104 hours were compensated. [Serbo-Croat] Reaktor RA je radio prema planu rada za 1975. godinu, nacinjenom u decembru prethodne godine. Planirano je da reaktor radi neprekidno prvih 10-20 dana u mesecu na nominalnoj snazi, tri sledeca dana je rezervisano za rad na drugim snagama zavisno od potreba korisnuka. Planirane su i 4 izmene goriva. Podaci o planiranom i ostvarenom radu kao i odstupanjima od plana i kracim prekidima u radu reaktora dati su u tabelama ovog priloga. Vidi se da su sva odstupanja i prekidi u ukupnom trajanju od 104 sata u celini nadoknadjeni.

  20. RA Research reactor Annual report 1981 - Part 1, Operation, maintenance and utilization of the RA reactor; Istrazivacki nuklearni reaktor RA, Deo 1 - Pogon, odrzavanje i eksploatacija reaktora u 1981. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Milosevic, M; Martinc, R; Kozomara-Maic, S; Cupac, S; Radivojevic, J; Stamenkovic, D; Skoric, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1981-12-15

    biggest difficulty was maintenance of reactor instrumentation. During 1981 the reactor was operated safely, there was no accident nor incident that would affect the safety of reactor personnel or the environment. The testing operation will be continued in 1982,and the experience so far shows that the program would be successfully fulfilled on the whole. [Serbo-Croat] Nuklearni reaktor RA prestao je sa radom nakon martovske kampanje 1979. godine usled pojave talozenja oksihidrata aluminijuma na kosuljicama gorivnih elemenata. Odgovarajucim resenjima Sanitarnog inspektorata Republickog sekretarijata za zdravje i socijalnu politiku SR Srbije i generalnog direktora Instituta za nuklearne nauke 'Boris Kidric', Vinca zabranjen je dalji rad reaktora sve dok se ne utvrde uzroci stvaranja oksihidrata aluminijuma i njihovog talozenja, preduzmu mere za njihovo uklanjanje i ne obezbede potrebni uslovi za normalan nastavak rada reaktora. Do kraja 1979. i tokom 1980. godine, nakon niza izvrsenih analiza i utvrdjivanja uzroka koji su doveli do zaustavljanja rada reaktora, izvrsene su sve neophodne pripreme za ponovno pustanje reaktora u rad. Polazeci od cinjenice da na reaktoru RA ne postoji sistem za hladjenje jezgra u slucaju udesa i da ne postoji adekvatan sistem za filtriranje potencijalno zagadjenog vazduha, a saglasno sa novim propisima o pustanju u rad i probnom radu nuklearnih objekata, Sanitarni inspektorat je doneo privremeno resenje kojim se dozvoljava pustanje reaktora u rad, tj. izvodjenje tzv. 'nultog eksperimenta' uz ogranicenje snage na 1% od vrednosti nominalne snage. Na osnovu dobijene dozvole, reaktor RA je ponovo pusten u rad 21. januara 1981. godine, kada je dostignuta kriticnost sa jezgrom sastavljenim iskljucivo od gorivnih elemenata od 80% obogacenog uranijuma. Eksperiment je zavrsen krajem marta, nakon cega je zatrazena dozvola za probni rad na vecim snagama i potom za rad na punoj snazi. Uzimajuci postojece stanje reaktora RA doneto je resenje kojim se

  1. Study of the absorbers and gaps influence on the reactor reactivity, IZ-061-0071-1961; Ispitivanje uticaja apsorbera i supljina na reaktivnost reaktora, IZ-061-0071-1961

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    It has been foreseen by the contract to study theoretically and experimentally the influence of the absorbers and gaps on the reactivity of the reactor. Within theoretical study it was planned to develop a method and find the approximation methods for calculations of these effects. Experimental part include development of equipment and performing the experiment at the RB reactor. Since it has not been possible to perform the experiment due to lack of heavy water, only the theoretical part of the task was completed with additional theoretical study of the VISA-1 experimental loop. This report includes the following annexes: influence of absorbers and gaps on the reactivity of the reactor, and calculation of flux depression in the VISA-1 loop. [Serbo-Croat] Ugovor predvidja teorijske i eksperimentalne radove u vezi ispitivanja uticaja apsorbera i praznina na reaktivnost reaktora. Za teorijski deo predvidjena je razrada metode i nalazenje aproksimativnih metoda za proracun ovih efekata. Eksperimentalni deo predvidja pripremu uredjaj i izvodjenje eksperimenata na reaktoru RB. S obzirom na nedostatak teske vode i nemogucnost izvodjenja eksperimenata, zadatak je obavljan samo teorijski a dodata mu je i teorijska obrada petlje VISA-1. Zadatak sadrzi sledece priloge: uticaj apsorbera i supljina na reaktivnost reaktora i proracun depresije fluksa u petlji VISA-1.

  2. Opinion about difficulties of RA reactor operation under conditions of high activity of the heavy water system - Annex 2; Prilog 2 - Misljenje o teskocama eksploatacije reaktora RA u uslovima visoke aktivnosti teskovodnog sistema

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    It was concluded that reactor the reactor operation is very dangerous for the reactor installation as well as safety of the staff under conditions of heavy water increased activity. Two fundamental arguments in favour of this conclusion are: insufficient possibility of reactor components inspection during maintenance and operation in the future period; difficulties in prevention of accidents that could occur is equally dangerous for the reactor facility and the environment. Cleaning and decontamination of the complete heavy water system is needed before the reactor operation starts in order to avoid possible failures or accidental events. [Serbo-Croat] Zakljuceno je da je eksploatacija reakora u uslovima postojece aktivnosti teskovodnog sistema veoma opasna po sam reaktor i po personal. Dva osnovna razloga u prilog ovog zakljucka su: nedovoljna mogucnost kontrole ispravnosti svih elemenata reaktora u toku remonta i ekspolatacije u predstojecem periodu; teskoca borbe sa udesima, koji bi se eventualno dogodili podjednako je opasna po instalaciju i okolinu. Pre no sto se nastavi sa daljom ekspolatacijom reaktora potrebno ciscenje, dekontaminacija sistema teske vode kako bi se izbegla moguca ostecenja ili akcidentalne situacije.

  3. Radiation protection at the RA Reactor in 1997, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Prilog 1 - Zastita od zracenja kod reaktora RA u 1997. godini - Deo 2 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, R; Kalinic, S [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1997-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1997. Actions in 1997 were focused to detailed analysis of the conditions of storing the spent fuel in the storage pools and preparing the documentation for decision making about the methods for the improvement of the mentioned conditions. After adopting the procedures, detailed preparations, and purchasing the needed equipment, the first phase of remedial action, the removal of the sludge from the bottom of the spent fuel storage pool was started in September 1997. It is stated that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni

  4. Radiation protection at the RA Reactor in 1996, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Prilog 1 - Zastita od zracenja kod reaktora RA u 1996. godini - Deo 2 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, R; Kalinic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1996-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1996. Actions in 1996 were focused to detailed analysis of the conditions of storing the spent fuel in the storage pools and preparing the documentation for decision making about the methods for the improvement of the mentioned conditions. It is stated that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. U 1996. godini nastavljena je akcija zapoceta prethodne

  5. Experimental operation of the RA reactor with 4 fuel channels containing 80% enriched dispersion fuel - Operational Report; Radni izvestaj - Eksperimentalna kampanja reaktora RA sa 4 kanala sa 80% obogacenim disperzionim gorivom

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Milosevic, M; Cupac, S; Kozomara, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    usmerene su na prelazni rezim na bazi parcijalnog uvodjenja novog goriva u reaktor, tj. na reaktorsko jezgro sa dve vrste goriva. Cilj ovih analiza i priprema jeste obezbedjivanje svih uslova za siguran rad reaktora RA u prelaznom rezimu. Ove analize i pripreme su uglavnom kompletirane. Medjutim, nedostaje jos eksperimentalni podatak o utrosku goriva za odredjeni rad reaktora na nominalnoj snazi tj. o dnevnom padu ugradjenog viska reaktivnosti. Ovaj podatak neophodan je kod planiranja izmena goriva (kolicine svezeg goriva i ucestanosti izmena) u prelaznom rezimu. Do ovog podatka moze se doci samo putem normalnog rada reaktora u toku vremena znatno duzeg od vremena u kome se uspostavlja ravnotezno zatrovanje, kao vremena izmedju dva prelivanja D{sub 2}O kondenzata u aktivnu zonu RA. U tom smislu je planirana desetodnevna eksperimentalna kampanja u decembru 1976. U ovom izvestaju izlozeni su oni najznacajniji rezultati sigurnosnih analiza i priprema koji ukazuju na potpunu sigurnost rada reaktora tokom ove eksperimentalne kampanje, sa aspekta postovanja ogranicenja najvaznijih parametara koji uticu na sigurnost reaktora, kao sto su reaktivnost, toplotna i temperaturska ogranicenja za gorivo i za reaktor, itd. Podaci koji budu dobijeni iz ove eksperimentalne kampanje su od znacaja jer ce se na osnovu njih konacno definisati dalji protok svezeg novog goriva, tokom prelaznog rezima (author)

  6. Dosimetry and technical radiation protection at the RA in 1974; Dozimetrija i tehnicka zastita od zracenja kod reaktora RA u 1974. godini

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1975-01-15

    This report include the analysis of the dosimetry and technical radiation protection results collected during 1974. The first part shows the data about the fundamental exposure to radiation and the statistical review of the total number of measurements. The following are included as well: measured values of radioactive gases and aerosol contents in air; contamination level of surfaces, clothes and uncovered parts of the staff bodies. Analysis of the personnel exposure is presented in the second part of the report. It was stated that the maximum individual external dose was 2.13R, and the exposure dose was 1/5 lower than of the annual dose limit for 90% of the exposed personnel. It was estimated that that the internal contamination is negligible compared to the external contamination. This statement was based on the frequency of tasks in the contaminated zones, undertaken control and protection measures, as well as on the evaluation of the expected internal contamination. Comparative evaluation of the occupational exposures is given for the past five years. This showed that the exposure in 1974 was lower than during previous years. The third part of the report covers the numerical data about the quantity of the collected radioactive waste, total size of contaminated and decontaminated surfaces and number of decontaminated objects. A brief analysis of the accidents occurred during this year under regular reactor operating conditions, maintenance and repair is given at the end. It was stated that there has been no accident that would cause exposure higher than the prescribed limits or any significant contamination of the working space or environment. Maximum individual dose was 1.4 R, and contamination of the uncovered parts of the bodies was about 6 MDNK (maximum permissible contamination level) [Serbo-Croat] U ovom radu prikazani su rezultati sakupljeni u toku godine u okviru dozimetrijske kontrole i tehnicke zastite kod reaktora. U prvom delu rada izlozeni su

  7. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1983; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1983. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Raickovic, N; Radivojevic, J; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1983-12-15

    After regular shutdown in November 1982, inspection of the fuel elements from the RA reactor core which was done from December 1982 - February 1983 has shown that there are deposits of aluminium oxides on the surface of the fuel cladding. After restart The RA reactor was operated at power levels from 1.8 - 2 MW, with 80% enriched uranium dioxide fuel elements. It was found that there was no corrosion of the fuel element cladding and that it was not possible to find the cause of surface deposition on the cladding surfaces without further operation. It was decided to purify the heavy water permanently during operation and to increase the heavy water flow by operating two pumps. This procedure was adopted in order to decrease the possibility of corrosion. The Safety committee of the Institute has approved this procedure for operating the RA reactor in 1983. The core was made of 80% enriched fuel, critical experiments were done until June 1983, and after that the operation was continued at power levels up to 2 MW. [Serbo-Croat] Pregledom nuklearnog goriva iz tehnoloskih kanala reaktora RA koji je izvrsen u periodu decembear 1982-feburuar 1983. godine nakon zaustavljanja reaktora po isteku novembarske kampanje 1982. godine, ustanovljeno je da ponovo dolazi do stvaranja taloga u obliku hidratisanih oksida aluminiuma na kosuljicama gorivnih elemenata. Nakon ponovnog pustanja u rad, reaktor je do novembra 1981. godine neprekidno bio u pogonu na snagama 1,8 - 2 MW. Jezgro je bilo formirano iskljucivo sa od gorivnih elemenata sa 80% obogacenim uran dioksidom. Utvrdjeno je da kosuljica gorivnog elementa nije korodirala, i da se bez nastval rada ne moze utvrditi uzrok pojave taloga na povrsini kosuljice. Da bi se mogucnost korozije aluminjumskih komponenti u primarnom kolu raktora svela na sto manju meru odluceno je da se vrsi neprekidno preciscavanje teske vode i da se istovremeno poveca protok teske vode radom dve pumpe, Komitet za sigurnost Instituta odobrio je ovakav nacin

  8. The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II

    Energy Technology Data Exchange (ETDEWEB)

    Loewenstein, W. B. [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    hexagonal del reactor los datos obtenidos en geometrias simples idealizadas, analiticas o experimentales. Se compara el rendimiento nuclear, incluso el de reproduccion, del reactor real con el del modelo teorico y se describen las variaciones a largo plazo de la reactividad y de la generacion de energia en la envoltura fertil, refiriendolas a los ciclos propuestos para el combustible y la envoltura fertil. La memoria formula consideraciones sobre la seguridad estudiando en particular la introduccion de indices de reactividad normales y anormales y la consecuencia de supuestos efectos de reactividad, que se basan en el comportamiento fisico de la aleacion combustible y de la estructura del reactor, asi como en la extrapolacion al sistema del EBR-II de los experimentos realizados con el conjunto TREAT. Por ultimo, examina el problema de la fusion del cuerpo del reactor EBR-II. (author) [Russian] Vychisleniya statisticheskogo, dinamicheskogo i dlitel'nogo rezhima reaktivnosti ehksperimental'nog o reaktora-razmnozhitel ya EBR-II dayutsya sovmestno s rezul'tatami i analizom ehksperimentov na reaktore EBR-II po dostizheniyu kritichnosti v sukhom sostoyanii i otdel'nykh ehksperimentov na reaktore ZPR-III. Osoboe vnimanie udelyaetsya problemam fizicheskogo rascheta reaktora, kotorye voznikayut posle opredeleniya printsipial'noj skhemy i do sooruzheniya ili vvoda reaktora v ehkspluatatsiyu. Opisyvayutsya analiz bezopasnosti reaktora i soobrazheniya po otsenke opasnostej, a takzheikh vliyanie na raschet reaktora. V doklade opisyvaetsya sposob ispol'zovaniya modeli EBR-II na osnovanii poluchennykh na reaktore ZPR-III dannykh, a takzhe dannykh sukhoj kritichnosti reaktora EBR-II. EHti ehksperimenty, ikh analiz i teoreticheskie vykladki yavlyayutsya osnovoj dlya opredeleniya fizicheskogo povedeniya reaktornoj sistemy. Bolee podrobno issleduyutsya ogranicheniya, prisushchie primeneniyu ehksperimental'nykh dannykh k rassmatrivaemo j ehnergeticheskoj reaktornoj sisteme. Syuda otnosyatsya

  9. Theoretical analysis of nuclear reactors (Phase I), I-V, Part V, Determining the fine flux distribution; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, V Deo, Odredjivanje fine raspodele fluksa

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    Mono energetic neutron transport equation was solved by Carlson numerical method in cylindrical geometry. S{sub n} code was developed for the digital computer ZUSE Z23. Neutron flux distribution was determined for the RA reactor cell by applying S{sub 4} approximation. Reactor cell was treated as D{sub 2}O-U-D{sub 2}O system. Time of iteration was 185 s. Resena je transportna monoenergetska jednacina numerickom metodom Carlsona u cilindricnoj geometriji. Razvijanje S{sub n} kod za digitalnu masinu ZUSE-Z 23. Odredjena je raspodela fluksa u celiji reaktora RA S{sub 4} aproksimacijom. Celija je tretirana kao D{sub 2}O-U-D{sub 2}O. Vreme iteracije je 185 sec (author)

  10. Safety analysis for testing operation of the RA reactor in the Boris Kidric Institute, Vinca; Analiza sigurnosti rada reaktora 'RA' za probni rad u Institutu za nuklearne nauke 'Boris Kidric' - Vinca

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-09-15

    This safety report covers detailed description of the RA reactor core, reactor components, coolant system, control system, safety system, reactor building including site characteristics. A separate chapter is devoted to radiation protection and radioactive waste management. Organizational structure od the reactor staff as well as training program are included. The last chapter includes detailed emergency plans for three accidents classified in three categories. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis reaktora RA, sistema za hladjenje, kontolno-sigurnosnog sistema, elektricnog sistema, zgrade sa instalacijama, ukljucujuci karakteristike lokacije. Posebno poglavlje opisuje sistem zastite od zracenja i rukovanje radioaktivnim otpadom. Opisana je organizacija rada i program obuke osoblja. Poslednje poglavlje sadrzi detaljan plan mera za slucaj udesa klasifikovanih u tri kategorije.

  11. Temperature measurement of the reactor materials samples irradiated in the fuel channels of the RA reactor - Annex 16; Prilog 16 - Merenje temperature uzoraka reaktorskih materijala ozracivanih u gorivnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M; Djalovic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    Reactor materials as graphite, stainless steel, magnox, zirconium alloys, etc. were exposed to fast neutron flux inside the fuel elements specially adapted for this purpose. Samples in the form ampoules were placed in capsules inside the fuel channels and cooled by heavy water which cools the fuel elements. In order to monitor the samples temperature 42 thermocouples were placed in the samples. That was necessary for reactor safety reasons and for further interpretation of measured results. Temperature monitoring was done continuously by multichannel milivoltmeters. This paper describes the technique of introducing the thermocouples, compensation instruments, control of the cold ends and adaptation of the instruments for precision (0.5%) temperature measurement in the range 30 deg - 130 deg C; 30 deg - 280 deg C and 30 deg - 80 deg C. Ozracivanje uzoraka materijala za izgradnju reaktora kao sto su grafit, nerdjajuci celik, magnox, legure cirkonijuma, aluminijuma itd. vrseno je u fluksu brzih neutrona unutar samih gorivnih elemenata koji su specijalno adaptirani za ovu svrhu. Uzorci u vidu ampula smesteni su u kapsulu od aluminijuma i postavljeni unutar kanala gde su hladjeni cirkulacijom teske vode koja hladi same gorivne elemente. U cilju kontrole temperature uzoraka radi bezbednosti samog reaktora, kao i radi kasnije interpretacije rezultata ispitivanja radijacionog ostecenja materijala, ugradjeno je 42 termopara u uzorke. Kontrola temperature je vrsena kontinualno visekanalnim registratorima. U radu je prikazana tehnika izvodjenja termoparova, kompenzacionih vodova, kontrola hladnih krajeva i prilagodjenje instrumentacije za merenje i registraciju temperature sa tacnoscu 0,5% u opsezima 30 deg - 130 deg C; 30 deg - 280 deg C i 30 deg - 80 deg C (author)

  12. Safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Vol. VI; Album VI: Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-07-01

    First part of the safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels contains descriptions of the independent CO{sub 2} loop, system for regulation, measurement and control od the loop parameters, description of the dosimetry system, and the plan for testing the experimental device before start-up. Second part of this analysis describes the influence of of the experimental device on the reactor operation under steady state conditions as follows: influence of the head of the independent coolant loop on the reactivity of the reactor core and influence on the reactor temperature coefficient. Third part of the report includes the analysis of possible accidents during operation of the independent CO{sub 2} coolant loop in the reactor. Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA sadrzi u prvom delu: opis nezavisnog kola CO{sub 2}, sistema za regulaciju, merenje i kontrolu parametara nezavisnog kola, sistema dozimetrijske kontrole i plan ispitivanja eksperimentalnih uredjaja pre pustanja u rad. Drugi deo ove analize obuhvata uticaj eksperimentalnog uredjaja na reaktor u normalnom rezimu rada i to: uticaj glave petlje nezavisnog kola CO{sub 2} za hladjenje uzoraka na reaktivnost reaktora i uticaj uredjaja na temperaturni koeficijent reaktora. Treci deo sadrzi analizu mogucih akcidenata u toku rada nezavisnog kola CO{sub 2} u reaktoru.

  13. Power Reactor Design at Zero Power; Etudes de Reacteurs de Puissance, au Moyen de Machines de Puissance Zero; Konstruktsiya ehnergeticheskogo reaktora nulevoj moshchnosti; Diseno de Reactores Generadores con Ayuda de Reactores de Potencia Nula

    Energy Technology Data Exchange (ETDEWEB)

    Redman, W. C.; Plumlee, K. E.; Baird, Q. L. [Argonne National Laboratory, Argonne, IL (United States)

    1964-02-15

    revela que el Laboratorio de Argonne ha venido basindose ampliamente en los sistemas exponenciales y criticos para llevar a cabo sus trabajos en materia de estudio de reactores. Los autores sugieren el papel futuro de estos sistemas al resumir brevemente los programas de trabajo, en curso de ejecucion o en proyecto, mediante los reactores de potencia nula que actualmente existen en Argonne y los que ese Laboratorio proyecta construit. (author) [Russian] Rjalis- sledovatel'skih reaktorov dlja central'nyh jelektrostancij, reaktorov v kachestve dvigate- lej, reaktorov dlja proizvodstva izotopov i ispytatel'nyh reaktorov byl issledovan na Argonskih reaktorah nulevoj moshhnosti, a svjazannye jeksponencial'nye i chisto kriticheskie sborki pozvolili poluchit' osnovnye dannye. Dlja togo, chtoby dat' nagljadnoe predstavle- nie o poslednih jeksperimentah i prodemonstrirovat' bol'shoe raznoobrazie dannyh o kon- strukcii reaktora, kotorye mozhno poluchit' v sistemah s maloj plotnost'ju nejtronnogo poto- ka, rassmatrivajutsja sledujushhie jeksperimental'nye programmy: 1. Izuchenie svojstv torievo-uranovogo topliva v tjazheloj vode s osobym uporom na trebova- nija, pred{sup j}avljaemye k konstrukcii vtoroj aktivnoj zony dlja Argonskogo jeksperimental'- nogo kipjashhego reaktora. 2. Maket predpologaemogo issledovatel'skogo reaktora s vysokoj plotnost'ju nejtronnogo potoka dlja podtverzhdenija raschetov konstrukcii, vybora optimal'noj geometrii i ocenki vlijanija vygoranija topliva. 3. Opredelenie harakteristik raspredelenija jenergii i vlijanija na reaktivnost' zatoplenija toplivnogo jelementa dlja kombinirovannyh ispytanij kipjashhego reaktora s peregrevom. 4. Konstrukcija aktivnoj zony proizvodjashhego plutonij reaktora-razmnozhitelja na bystryh nejtronah na urane - 235 s natrievym ohlazhdeniem kak pervoj zagruzki dlja Argonskogo jeksperimental'nogo reaktora-razmnozhitelja II. 5. Issledovanie harakteristik reaktora s vzaimodejstvujushhimi zonami na teplovyh i byst- ryh nejtronah. Pri

  14. Radiation protection at the RA Reactor in 1990, Part -2, Control of the working environment, dosimetry and radiation protection, Annex 1; Deo - 2, Zastita od zracenja kod reaktora RA u 1990. godini, Prilog 1 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Raicevic, J; Bjelanovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1990-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. It was found that the individual dose from external exposure during previous ten months was less than 2.5 mSv, and that single exposures of the staff was less than 1/10 of the annual dose limit. Comparison with the data for previous five years shows that the exposures in 1990 were lower than during past five years. It is stated that there has been no accident that would result in significant surface contamination. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila manja od 2,5 mSv a da su pojedinacna izlaganja radnog

  15. Radiation protection at the RA Reactor in 1989, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Zastita od zracenja kod reaktora RA u 1989. godini - Deo 2, Prilog 1 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Glodic, S; Raicevic, J; Pavlovic, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. It was found that the individual dose from external exposure during previous ten months was less than 4.0 mSv, and that single exposures of the staff was less than 1/10 of the annual dose limit. Comparison with the data for previous five years shows that the exposures in 1989 were lower than during past five years. It is stated that there has been no accident that would result in significant surface contamination. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila manja od 4,0 mSv a da su pojedinacna izlaganja radnog

  16. Radiation protection at the RA reactor in 1987, Part I: Control of the working environment - dosimetry and radiation protection at the RA reactor, Annex 1; Prilog 1, Zastita od zracenja kod reaktora RA u 1987. godini - Deo 1: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Laboratory for radiation and environmental proetecion, Beograd (Serbia and Montenegro)

    1987-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted was less than 6.0 mSv during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. During 1987 there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 6,0 mSv, a da su pojadinacna izlaganja vise od 9/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina, iz kojih

  17. Radiation protection at the RA Reactor in 1985, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Zastita od zracenja kod reaktora RA u 1985. godini - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 8.2 mSV during past 10 months. Individual exposures for 7/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1985. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 8.2 mSv, a da su pojedinacna izlaganja vise od 7/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o

  18. RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1988; Istrazivacki nuklearni reaktor RA, deo 1, pogon i odrzavanje nukleanog reaktora RA u 1988. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1988-12-15

    According to the action plan for 1988, operation of the RA reactor should have been restarted in October, but the operating license was not obtained. Control and maintenance of the reactor components was done regularly and efficiently dependent on the availability of the spare parts. The major difficulty was maintenance of the reactor instrumentation. Period of the reactor shutdown was used for repair of the heavy water pumps in the primary coolant loop. With the aim to ensure future safe and reliable reactor operation, action were started concerning renewal of the reactor instrumentation. Design project was done by the soviet company Atomenergoeksport. The contract for constructing this equipment was signed, and it is planned that the equipment will be delivered by the end of 1990. In order to increase the space for storage of the irradiated fuel elements and its more efficient usage, projects were started concerned with reconstruction of the existing fuel handling equipment, increase of the storage space and purification of the water in the fuel storage pools. These projects are scheduled to be finished in mid 1989. This report includes 8 annexes concerning reactor operation, activities of services and financial issues. [Serbo-Croat] Prema planu za 1988. godinu, reaktor RA je trebalo da pusten u rad oktobra meseca, medjutim nije dobio dozvolu za nastavak rada. Kontrola i odrzavanje opreme izvrsavani su redovno i efikasno, u granicama koje su diktirane raspolozivoscu repromaterijala i rezervnih delova. Najvecu poteskocu pricinjavalo je odrzavanje instrumentacije. Period stajanja u 1988. godini iskoriscen je za remont teskovodnih pumpi u primarnom kolu hladjenja. U cilju povecanja pouzdanosti rada reaktora zapoceti su radovi na modernizaciji instrumentacije, projekat je izradjen u sovjetskoj organizaciji Atomenergoeksport, sklopljen je ugovor o izradi ove opreme koja bi trebalo da bude isporucena do kraja 1990. U cilju povecanja prostora za skladistenje ozracenog

  19. Calculated activities of some isotopes in the RA reactor highly enriched fuel significant for possible environmental contamination - Operational report; Radni izvestaj - Proracun aktivnosti nekih izotopa u visokoobogacenom uranskom gorivu reaktora RA, znacajnih sa gledista moguce kontaminacije okoline

    Energy Technology Data Exchange (ETDEWEB)

    Bulovic, V; Martinc, R; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    This report contains calculation basis and obtained results of activities for three groups of isotopes in the RA reactor 80% enriched fuel element. The following isotopes are included: 1) {sup 85m}Kr, {sup 87}Kr, {sup 88}Kr, {sup 131}J, {sup 132}J, {sup 133}J, {sup 134}J, {sup 135}J, {sup 133}Xe, {sup 138}Xe i {sup 138}Cs, 2) {sup 89}Sr, {sup 90}Sr, {sup 91}Sr, {sup 92}Sr, {sup 95}Zr, {sup 97}Zr, {sup 103}Ru, {sup 105}Ru, {sup 106}Ru, {sup 129m}Te, {sup 134}Cs, {sup 137}Cs, {sup 140}Ba, {sup 144}Ce, kao i 3) {sup 238}Pu, {sup 239}Pu i {sup 240}Pu. It was estimated that the fuel is exposed to mean neutron flux. The periodicity of reactor operation is taken into account. Calculation results are given dependent on the time of exposure. These results are to be used as source data for Ra reactor safety analyses. [Serbo-Croat] Izlozene su osnove i prikazani su rezultati izvedenog proracuna aktivnosti tri grupe izotopa u gorivnom elementu reaktora RA sa 80% obogacenim uranom - 235. Obuhvaceni su: 1) {sup 85m}Kr, {sup 87}Kr, {sup 88}Kr, {sup 131}J, {sup 132}J, {sup 133}J, {sup 134}J, {sup 135}J, {sup 133}Xe, {sup 138}Xe i {sup 138}Cs, zatim, 2) {sup 89}Sr, {sup 90}Sr, {sup 91}Sr, {sup 92}Sr, {sup 95}Zr, {sup 97}Zr, {sup 103}Ru, {sup 105}Ru, {sup 106}Ru, {sup 129m}Te, {sup 134}Cs, {sup 137}Cs, {sup 140}Ba, {sup 144}Ce, kao i 3) {sup 238}Pu, {sup 239}Pu i {sup 240}Pu. Pretpostavljeno je da se gorivo ozracuje na srednjem fluksu neutrona, a periodicnost rada reaktora je uvazavana. Rezultati proracuna, dati u numerickom obliku, sistematizovani su kao funkcija toka vremena ozracivanja goriva. Ovi rezultati bice korisceni kao izvorni podaci kod izrade sigurnosnih analiza za reaktor RA (author)

  20. Dispersion-Type Absorbing Materials for the Control Organs of Thermal Reactors; Absorbants du Type a Dispersion pour les Organes de Commande des Reacteurs a Neutrons Thermiques; Pogloshchayushchie materialy dispersionnogo tipa dlya organov regulirovaniya teplovykh reaktorov; Absorbentes de Tipo Dispersion para los Organos de Mando de los Reactores Termicos

    Energy Technology Data Exchange (ETDEWEB)

    Nosov, V. I.; Ponomarjov-Stepnoj, H. H.; Portnoj, K. I.; Savel' ev, E. G.

    1964-06-15

    type nimonik auxquels on a ajoute des. oxydes de terres rares ont des caracteristiques d'endurance et des.caracteristiques thermo-physiques d'une valeur relativement elevee (o{sub B}, E, {lambda}) a des temperatures elevees pour les valeurs de la concentration de l 'absorbant voisines de 10%. Les materiaux du type a dispersion de ce genre ont une radioresistance satisfaisante dans un champ de rayonnement ( Tilde-Operator 3 * 10{sup 20}n/cm{sup 2}) aux hautes temperatures. (author) [Spanish] Los autores exponen los resultados de su estudio de las caracteristicas fisicas de las aleaciones absorbentes del tipo 'nimonic' con oxidos de las tierras raras (gadolinio, samario, europio, etc.) dispersos en ellas. Examinan las variaciones de la capacidad de absorcion segun la composicion del material, indican las propiedades mecanicas y termofisicas de los materiales absorbentes en funcion de la concentracion del absorbente incorporado a la aleacion y, por ultimo, presentan los resultados de un estudio acerca de los efectos de la irradiacion sobre esas propiedades. . Demuestran que las aleaciones absorbentes que contienen oxidos de las tierras raras dispeisos en la matriz metalica poseen una elevada capacidad de absorcion para una proporcion relativamente baja de absorbente en la aleacion ( Tilde-Operator 5 a 10%). Las caracteristicas de resistencia y las propiedades termofisicas (o{sub B}, E, {lambda}) de las aleaciones del tipo 'nimonic' con adicion de oxidos de las tierras raras asumen valores comparativamente elevados al ascender la temperatura, cuando la concentracion del absorbente es del orden del 10%. A temperaturas elevadas los materiales de tipo dispersion de esa indole ofrecen una radiorresistencia satisfactoria dentro del campo de irradiacion estudiado ( Tilde-Operator 3 x 10{sup 20} n/cm{sup 2}). (author) [Russian] Privodjatsja rezul'taty issledovanija fizicheskih harakteristik pogloshhajushhih splavov tipa nimonik s dispergirovannymi v nih okislami redkozemel

  1. Nondestructive analysis of RA reactor fuel burnup, Program for burnup calculation base on relative yield of {sup 106}Ru, {sup 134}Cs and {sup 137}Cs in the irradiated fuel; Nedestruktivno odredjivanje izgaranja goriva reaktora RA, Program za izracunavanje izgaranja na osnovu relativne zastupljenosti {sup 106}Ru, {sup 134}Cs i {sup 137}Cs u ozracenom gorivu

    Energy Technology Data Exchange (ETDEWEB)

    Bulovic, V F [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1971-07-01

    Burnup of low enriched metal uranium fuel of the RA reactor is described by two chain reactions. Energy balance and material changes in the fuel are described by systems of differential equations. Numerical integration of these equations is base on the the reactor operation data. Neutron flux and percent of Uranium-235 or more frequently yield of epithermal neutrons in the neutron flux, is determined by iteration from the measured contents of {sup 106}Ru, {sup 134}Cs and {sup 137}Cs in the irradiated fuel. The computer program was written in FORTRAN-IV. Burnup is calculated by using the measured activities of fission products. Burnup results are absolute values. Sagorevanje maloobogacenog uranskog metalnog goriva reaktora RA je opisano dvema lancanim reakcijama. Energetski bilans i materijalne promene u gorivu su opisane sistemima diferencijalnih jednacina. Numericka integracija jednacina se vrsi na osnovu podataka u dinamici rada reaktora. Fluks reaktorskih neutrona i procenat urana-235 ili ucesce epitermalnih neutrona u fluksu, odredjuje se iterativno na osnovu izmerenog sadrzaja {sup 106}Ru, {sup 134}Cs i {sup 137}Cs u ozracenom gorivu. Program je napisan u FORTRAN-u IV u jednom bloku, bez podprograma. Izracunavanje izgaranja je zasnovano na izmerenim kolicnicima aktivnosti fisionih produkata. Rezultati izgaranja imaju apsolutni karakter (author)

  2. Theoretical analysis of nuclear reactors (Phase II), I-V, Part V, Determining the fine neutron flux distribution by Pn method; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, V Deo, Odredjivanje fine raspodele fluksa Pn metodom

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    Expression for spherical harmonic moments were applied. They were obtained by spherical harmonics expansion of monoenergetic transport equation. This report presents the procedure for calculating the neutron flux distribution in the nine-zone reactor cell of the RA reactor in Vinca. The procedure was modelled for digital computer ZUSE Z-23 by expansion of the diagram of the automated P{sub 3} code, which is adequate for P{sub n} code with minor changes. The needed subroutines were developed. The most important ones were those for modified first and second order Bessel functions of n-th order. Computer Z-23 was operating only 15 hours during three months, and thus only the subroutines for modified Bessel functions could be tested and the obtained results were excellent. For the mentioned reason the neutron flux distribution will be calculated in the forthcoming period. Koriscen je izraz za svernoharmonicne momente koji se dobija razvijanjem monoenergetske transportne jednacine u sverne harmonike. Dat je postupak za odredjivanje raspodele neutronskog fluksa u devet medijalnoj celiji reaktora RA u Vinci. Gornji postupak je logicki organizovan na digitalnoj masini ZUSE Z-23 razvijanjem tekuceg dijagrama automatskog P{sub 3} koda, koji sa malim izmenama odgovara Pn kodu. Razvijene su potrebne osnovne subrutine, medju kojima su najznacajnije one za modificirane Beselove funkcije prve i druge vrste n - tog reda. Masina ZUSE Z-23 bila je u radu svega 15 zasova u toku tri meseca, te sam stigao da testiram samo subrutine za modificirane Beselove funkcije koje su dale odlicne rezultate. Iz ovoga razloga nije se mogla dobiti trazena raspodela fluksa. To ce biti ucinjeno u narednom periodu posto cemo moci koristiti masinu Z-23 (author)

  3. Radiation protection at the RA Reactor in 1986, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 20.5 mSV during past 10 months. Individual exposures for 7/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1986. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 20,5 mSv, a da su pojadinacna izlaganja vise od 7/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o

  4. Radiation protection at the RA Reactor in 1988, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Glodic, S; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1988-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted was less than 0.5 mSv during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. During 1988 there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 0,5 mSv, a da su pojedinacna izlaganja vise od 9/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina, iz

  5. Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Vol. V; Album V: Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-07-01

    Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels includes the following: calculations of CO{sub 2} gas activity, design of the dosimetry control system, review of the changes that should be done in the RA reactor building for installing the independent CO{sub 2} loop, specification of the materials with cost estimation, engineering drawings of the system. Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA sadrzi: proracun aktivnosti gasa CO{sub 2}, idejno resenje sistema dozimetrijske kontrole, pregled izmena koje bi trebalo izvrsiti u zgradi RA u vezi montaze nezavisnog kola CO{sub 2}, specifikaciju materijala sa cenom kostanja i graficku dokumentaciju predprojekta.

  6. Radiation protection at the RA Reactor in 1986, Part -2, Annex 2a, Radioactivity control of the RA reactor environment (atmospheric precipitations, dust, water, soil, plants, fruit...); Deo 2 - Prilog 2a - Kontrola radioaktivnosti okoline nuklearnog reaktora RA (padavine i slobodno natalozena prasina, vode, zemljiste, rastinje, voce...)

    Energy Technology Data Exchange (ETDEWEB)

    Ajdacic, N; Martic, M; Jovanovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    Control of radioactivity in the biosphere in the vicinity of the RA reactor is part of the radioactivity control done regularly for the whole territory of the Vinca institute (report by the same authors included in this Annex). During 1986 control was conducted according to the plan until May 1, 1986 when a dramatic increase of the precipitations and all other samples from the biosphere was recorded. According to the measured data no significant changes have been found in the surroundings of the RA reactor, until April 29 1986. Since then more detailed control was conducted, the number of samples was increased, apart from standard measuring procedure of total beta activity measurements, gamma spectrometry of all samples was applied. High activity level of the following nuclides was found: Iodine, cerium,cesium, tellurium, ruthenium, barium, lanthanum, etc. As an example activity of ?1?3?1 I in one sample was 564{+-}5 kBq/m{sup 2}. [Serbo-Croat] Kontrola radioaktivnosti biosfere u okolini reaktora RA je deo kontrole radioaktivnosti koja se redovno vrsi za celokupnu teritoriju Instituta Vinca (izvestaj istih autora ukljucen je u ovaj Prilog). Tokom 1986. kontrola je ostvarivana prema planu do 1. maja 1986, kada je registrovano drasticano povecanje aktivnosti padavina i ostalih uzoraka biosfere. Prema rezultatima merenja, nisu registrovana znacajnija odstupanja u okolini reaktora RA sve do 29. aprila 1986. Od tada se vrse detaljnija merenja, broj uzoraka je uvecan, pored standardno primenjivane metode primenom merenja totalne beta aktivnosti uzoraka, svi uzorci su analizirani gama spektrometrijski. Enormno visoka kontaminacija uzoraka posle gamma spektrometrije pokazala je prisustvo aktivacionih i fisionih radionuklida medju kojima su bili: jod, cerijum, cesijum, rutenijum, barium lantan i drugi. Tako je na primer samo aktivnost I-133 iznosila 564{+-}5 kBq/m{sup 2}.

  7. Gemostaz u detey i vzroslykh s sakharnym diabetom 1 tipa

    Directory of Open Access Journals (Sweden)

    E I Kondrat'eva

    2007-12-01

    Full Text Available Цель. Провести сравнительный анализ состояния коагуляционного и тромбоцитарно-сосудистого гемостаза у детей, подростков и взрослых при CД 1. Материалы и методы. Обследовано 335 человек, из них 117 здоровых лиц и 118 детей, подростков и взрослых с СД 1 в возрасте от 11 до 50 лет, которые были разделены на 5 возрастных групп. Дизайн исследования ? простое, сравнительное. Материалом для исследования служила венозная и капиллярная кровь. Оценивали тромбоцитарный гемостаз, коагуляционный гемостаз, антикоагулянтное звено. Результаты. Исследование антикоагулянтных свойств выявило повышение уровня антитромбина III у больных в возрасте от 19 до 25 лет по сравнению со здоровыми людьми соответствующего возраста. Изучение сосудисто-тромбоцитарного гемостаза у данной категории больных выявило снижение содержания тромбоцитов у обследуемых в возрасте от 19 до 25 лет по сравнению с контролем. Хроническая гипергликемия вызывает повышение активности свертывающей системы крови у больных СД 1, что диктует необходимость строгого контроля за показателями гемостаза и коррекции выявленных нарушений. Заключение. Развитие сосудисто-тромбоцитарной дисфункции при сахарном диабете 1 типа не зависит от возраста. Для детей и подростков, больных сахарным диабетом 1 типа, характерно компенсаторное повышение активности антикоагулянтной системы. Активность фибринолитической системы у детей, подростков и взрослых, больных сахарным диабетом, превышает таковую в норме.

  8. Operating Experience with the VERA Zero-Energy Fast Reactor; Fonctionnement du Reacteur VERA a Neutrons Rapides, de Puissance Zero; Opyt ehkspluatatsii reaktora VERA na bystrykh nejtronakh nulevoj moshchnosti; Experiencia Adquirida con el Reactor Rapido VERA de Potencia Nula

    Energy Technology Data Exchange (ETDEWEB)

    Weale, J. W.; McTaggart, M. H.; Goodfellow, H.; Paterson, W. J. [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

    1964-02-15

    , intensidad de la fuente neutronica, empleo de un acelerador para producir neutrones; velocidad de respuesta de los circuitos de seguridad y restricciones subsiguientes en lo que atafle a la velocidad con que se pueden unir las dos mitados; precauciones adicionales necesarias al utilizar plutonio como combustible; notas sobre la precision de las mediciones de reactividad y sobre las limitaciones practicas que afectan a otras mediciones relacionadas con la fisica de los reactores. (author) [Russian] Daetsja kratkoe opisanie konstrukcii reaktora na bystryh nejtronah nule- voj moshhnosti, sostojashhego iz dvuh odinakovyh chastej. Pri jetom osoboe vnimanie udeljaetsja tem chertam, kotorye opredeljajut praktichnost' i obespechivajut tochnost' izmerenij po fizi- ke reaktorov. Obsuzhdajutsja preimushhestva i nedostatki konstrukcii s ssylkoj na dvuhlet- nij opyt jekspluatacii reaktora. Rassmatrivajutsja sledujushhie temy:prisposoblennost' proekta i konstrkcii iz dvuh odinakovyh chastej dlja provedenija jeksperimental'nyh issle- dovanij; razmer i kachestvo obrabotki toplivnyh blokov i tochnost' razmeshhenija toplivnyh jelementov; vlijanie granichnyh neravnomernostej i geterogennosti struktury na tochnost' opredelenija kriticheskoj massy ''ideal'noj'' jekvivalentnoj sborki; vosproizvodimost' kri- ticheskogo uslovija posle demontirovanija sborki ili razdelenija dvuh chastej; izmenenie reak- tivnosti s razdeleniem chastej, v tom chisle vlijanie nesimmetrichnoj zagruzki;chuvstvitel'- nost' razlichnyh schetchikov, moshhnost' istochnika nejtronov, ispol'zovanie istochnika uskorennyh nejtronov; bystrota otvetnoj reakcii konturov avarijnoj zashhity i posledujushhie ogranichenija skorosti sobiranija chastej; dopolnitel'nye predupreditel'nye mery, neobho- dimye pri ispol'zovanii plutonija; primechanija otnositel'no tochnosti izmerenija reaktiv- nosti i otnositel'no prakticheskih ogranichenij, vlijajushhih na razlichnye drugie izmerenija po fizike reaktorov. (author)

  9. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Energy Technology Data Exchange (ETDEWEB)

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    , ''Rejnish vestfalishes ehlektritsitetsverk und bajernverk'', Kal'-na-Majne, Zapadnaya Germaniya. Rabochaya kharakteristika kipyashchego reaktora atomnoj ehlektrostantsii pri obychnom rezhime raboty v kommunal'noj ehnergosisteme ochen' khoroshaya. Koehffitsient ispol'zovaniya i moshchnosti reaktora i ehlektrostantsii daet tverdoe osnovanie polagat', chto ehlektrostantsii s kipyashchimi reaktorami yavlyayutsya nadezhnymi s tochki zreniya ikh rabochej kharakteristiki. V techenie 1963 goda budut vvedeny v stroj chetyre dopolnitel'nye ehlektrostantsii s kipyashchimi reaktorami: atomnaya ehlektrostantsiya v Big Rok Pojnt, ''Kons'yumers pauehr kompani'', Sharl'vua, Michigan, atomnaya ehnergeticheskaya ustanovka v KHamboldt Bej, ''Pasifik gaz ehnd ehlektrik kompani'', Yurika, Kaliforniya, atomnaya ehlektrostantsiya v Garig'yano, Natsional'noe obshchestvo po atomnoj ehnergii, Skauri, Italiya,i Yaponskij demonstratsionnyj ehnergeticheskij reaktor. Yaponskij nauchno-issledovatel'skij institut po atomnoj ehnergii, Tokai-Mura, Yaponiya. Pusk i pervonachal'naya ehkspluatatsiya ehtikh ehlektrostantsij podtverzhdayut predpolozhenie o nadezhnosti ikh raboty, chto uzhe prodemonstrirovano atomnymi ehlektrostantsiyami v Drezdene, Kale i Vallesitose. Rabochaya kharakteristika atomnykh ehlektrostantsij v Drezdene, Kale i Vallesitose yavlyaetsya naglyadnym dokazatel'stvom stabil'nosti i bezopasnosti kipyashikh reaktorov. Krome togo, urovni radiatsii na samoj ehlektrostantsii i v okruzhayushchej srede znachitel'no nizhe predelov, ustanovlennykh litsenziyami na ehkspluatatsiyu. Podtverdilis' prostota i legkost' ehkspluatatsii kipyashchikh reaktorov. Kharakteristika kontrolya za nagruzkoj u kipyashchego reaktora s dvojnym tsiklom Drezdenskoj ehlektrostantsii okazalas' ochen' khoroshej. Krupnye i nebol'shie raboty po ukhodu i remontu mogut osushchestvlyat'sya obychnymi remontnymi gruppami bez vrednykh posledstvij ili bez limita vremeni, svyazannymi s soobrazheniyami radioaktivnogo oblucheniya. V

  10. Construction and Operation of a Commercial Gamma-Ray Package-Sterilizing Plant; Construction et fonctionnement d'une installation industrielle pour la sterilisation d'articles sous emballage par les rayons gamma; Razrabotka i ehkspluatatsiya sbornoj ustanovki gamma-izlucheniya promyshlennogo tipa dlya sterilizatsii meditsinskikh materialov; Construccion y funcionamiento de una instalacion industrial para la esterilizacion gamma de articulos medicos empaquetados

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, C. G. [Johnson' s Ethical Plastics Ltd., Slough (United Kingdom)

    1963-11-15

    Upravlenii po atomnoj ehnergii Soedinennogo Korolevstva), nastoyashchaya ustanovka byla sproektirovana spetsial'no dlya sterilizatsii plastmassovykh shpritsev i drugikh meditsinskikh materialov analogichnoj plotnosti. Ustanovka nachala funktsionirovat' s noyabrya 1962 goda. Dano opisanie osnovnykh kharakteristik i osobennostej e konstruktsii, priborov, obespechivayushchikh zashchitu obsluzhivayushchego personala, i metoda zagruzki sterzhnej. Opisan opyt ehkspluatatsii, vklyuchaya dozimetriyu, vklyuchenie ustanovki v edinyj tekhnologicheskij tsikl; privedeny rezul'taty bakteriologicheskikh issledovanij. Kratko obsuzhdeny ehkonomicheskie pokazateli pri sterilizatsii gamma-izlucheniem; dana otsenka vozmozhnosti primeneniya ustanovok podobnogo tipa v budushchem. (author)

  11. Safety report for the independent CO{sub 2} loop for cooling the samples irradiated in the vertical experimental channels of the RA reactor; Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracenih u vertikalnim eksperimentalnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, A; Zivkovic, S; Milosevic, M; Strugar, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    Independent CO{sub 2} loop was designed for cooling the samples irradiated in the vertical experimental channels in the region of heavy water or in the graphite reflector. It is considered as a significant improvement of the RA reactor experimental possibilities. Six 'heads' are placed in vertical experimental channels and connected in parallel with the outer loop which contains out-of-reactor equipment. It is planned to irradiate samples in the 'heads' of the loop for the needs of Hot laboratory and Laboratory for reactor materials. Heat generated during sample irradiation is removed by CO{sub 2} circulation. This report contains detailed description of the main loop, auxiliary systems, calculation results of anti reactivity and activation of construction materials of the low-temperature CO{sub 2} loop. A separate chapter is devoted to control and regulation of temperature and pressure. Testing of the fundamental parameters of the coolant loop showed that it could fulfill more demanding tasks than designed by the project. Annex of this report includes results of leak testing for the loop 'heads' in vertical experimental channels VEK-6 and VEK-8 by helium leak detector. [Serbo-Croat] Nezavisno kolo CO{sub 2} namenjeno je za hladjenje uzoraka ozracivanih u VEK reaktora u zoni teske vode i u zoni grafita, i predstavlja znacajan doprinos povecanju eksperimentalnih mogucnosti reaktora RA. Sest 'glava' je postavljeno u vertikalne eksperimentalne kanale i paralelno vezano na spoljno kolo koje sadrzi vanreaktorsku opremu. U glavama petlje se predvidja ozracivanje raznovrsnih uzoraka materijala za potrebe Laboratorije za visoku aktivnost i Laboratorije za reaktorske materijale. Toplota koja se generise prilikom ozracivanja uzoraka odvodi se cirkulacijom CO{sub 2}. Ovaj izvestaj sadrzi detaljan opis: glavnog kola, pomocnih sistema; rezultate proracuna antireaktivnosti i aktivacije konstrukcionih elemenata glave niskotemperaturne petlje CO{sub 2}. Posebno poglavlje posveceno

  12. RA Research reactor Annual report 1982 - Part 1, Operation, maintenance and utilization of the RA reactor; Istrazivacki nuklearni reaktor RA - Deo 1 - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1982. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Radivojevic, J; Stamenkovic, D; Skoric, M; Miokovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1982-12-15

    outdated spare parts. Project concerning renewal of the reactor equipment was initiated during the past year according to the contract with the Soviet Atomenergoexport and IAEA which has planned to spend 1 000 000 of rubles for this project. [Serbo-Croat] Probni rad reaktora zapocet septembra 1981. godine na snazi od 2 MW sa 80% obogacenim gorivom nastavljen je u celoj 1982. prema prethodno napravljenom planu. Pocetno jezgro formirano ja sa 44 gorivna kanala sa po deset gorivnih elemenata. Prva polovina godine iskoriscena je za neophodna merenja i ispitivanja radnih parametara rektora i funkcionisanje sistema i opreme u radnim uslovima. U drugoj polovini godine zapocet je program probnog rada na visim snagama. Utvrdjeno je da ugradjeni visak reaktivnosti i kapacitet kontrolnih sipki zadovoljava sigurnosne kriterijume MAAE, ugradjeni visak reaktivnosti moze da omoguci rad na snazi od 4,7 MW u 4 mesecne kampanje sa po 15-20 dana rada, postoje povoljni uslovi za hladjenje jezgra pri pocetnoj konfiguraciji. Izmeren je efekat pocetnog zatrovanja na reaktivnost i raspodelu snage, izmerena je pocetna prostorna raspodela neutronskog fluksa koja iznosi 3,9 10{sup 13} cm{sup -2} s{sup -1} pri znazi od 2 MW. Odredjena je promena kalibracionog koeficijenta u sistemu za automatsko odrzavanje snage. Svi rezultati ukazuju da ce pri nominalnoj snazi od 4,7 Mw biti zadovoljeni svi kriterijum sigurnosti i postovana ogranicenja u odnosu na koriscenje goriva. Po dobijanju dozvole za rad na punoj snazi morace da se izvrsi dopunski probni rad na snagama od 3, 4, i 4,7 MW. Prelaz od pocetne konfiguracije sa 44 gorivna kanala u jezgru vrsice se postupno da bi se dostigla ravnotezna konfiguracija sa 72 gorivna kanala sa po 10 elemenata. Reaktor nije radio u septembu mesecu zbog radova na zameni dela cevovoda koji povezuje pumpnu stanicu na Dunavu sa horizontalnim taloznikom. Kontrola i odrzavanje opreme izvrsavani su redovno u granicama raspolozivosti rezerbinh delova. Teskocu pricinjava

  13. Neutron Tests at the Start-Up of EDF1; Les essais neutroniques au demarrage du reacteur EDF1; Nejtronnye izmereniya pri puske reaktora EDF1; Ensayos neutronicos efectuados durante la puesta en marcha del reactor EDF1

    Energy Technology Data Exchange (ETDEWEB)

    Teste du Bailler, A. [Centre d' Etudes Nucleaires de Saclay (France); Janin, R. [Electricite de France, Paris (France)

    1963-10-15

    ehksperimental'nykh metodov, razrabotannykh na reaktorakh v Markule, byla provedena vo vremya puska reaktora EDF.1. Izmereniya kasalis' glavnym obrazom ehffektivnosti upravlyayushchikh sterzhnej pri razlichnykh p ogruzh eniyakh. Opredelyaetsya skhema pod''ema s terzhnej, kotoraya pozvolyaet poluchat' polnuyu moshchnost' prk soblyudenii opredelennykh ogranichenij v temperature obolochek i gaza. Parallel'no byli provedeny izmereniya potoka pri razlichnykh polozheniyakh kompensiruyushchikh sterzhnej i pri razlichnykh zagruzkakh poglotitelej v opredelennykh kanalakh, v zavisimosti ot predvaritel'nykh raschetov v dvukhraehmernom izmerenii. Ehti izmereniya byli polucheny putem aktivatsii tochechnykh detektorov s primeneniem obychnogo metoda otravleniya vozdukha. Pri nekotorykh urovnyakh temperatury (do 140{sup o}C) byli provedeny izmereniya koehffitsientov reaktivnosti i ehffektivnosti reguliruyushchikh sterzhnej. V to zhe vremya putem aktivatsii sootvetstvuyushchikh detektorov (uran, plutonij, lyutetsij, marganets, indij, zoloto) byli provedeny izmereniya koehffitsientov spektra. Dlya izmereniya ehffektivnosti nekotorykh kompensiruyushchikh sterzhnej byl ispol'zovan ostsillyatsionnyj metod. Nakonets, s tselyakh izucheniya zashchity i povrezhdeniya grafita byli provedeny izmereniya potoka bystrykh nejtronov. (author)

  14. Advanced epithermal thorium reactor (AETR) physics; Physique d'un reacteur au thorium, a neutrons epithermiques, de type perfectionne (AETR); Fizika usovershenstvovannog o nadteplovogo torievogo reaktora; Fisica del reactor epitermico de tipo avanzado, alimentado con torio (AETR)

    Energy Technology Data Exchange (ETDEWEB)

    Campise, A. V. [Atomics International, Canoga Park, CA (United States)

    1962-03-15

    del {sup 233}Pa y de isotopos del uranio sobre el balance neutronico relativo y se evalua la probable razon de reproduccion y las caracteristicas de combustion teniendo en cuenta la imprecision en el conocimiento de las secciones eficaces nucleares. (author) [Russian] Rassmatrivayuts ya printsipy konstruirovani ya usovershenstvovannog o nadteplovogo torievogo reaktora s uchetom sushchestvuyushchej teorii yadernykh parametrov i potentsial'nogo poleznogo ispol'zovaniya nejtronov. Byl izuchen ehffekt rezonansnogo zakhvata toriya v sistemakhs grafitovym zamedlitelem dlya nejtronov s ehnergiyami ot 0,10 do 100 kehv. Ispol'zuyutsya formuly uzkogo rezonansa i shirokogo rezonansa v tselyakh polucheniya zavisimogo ot temperatury ehffektivnogo rezo- nansnogo integrala torievogo sterzhnya, kotoryj vyrazhaetsya v vide ehkvivalentnykh mnogogruppovykh sechenij. Neobkhodimost' v poluchenii yadernykh dannykh v oblasti promezhutochnykh ehnergij privela k sozdaniyu proekta i konstruktsii kriticheskoj sborki. Yadernyj proekt ehtoj sborki podcherkivaet vazhnost' dannykh poperechnykh sechenij i teoreticheskoj interpretatsii ehksperimental'nykh rezul'tatov, imeyushchikh otnoshenie k usovershenstvovannom u nadteplovomu torievomu reaktoru. Tochnost' analiticheskikh metodov byla podtverzhdena pri analize ehksperimental'nykh rezul'tatov, poluchennykh na reaktore nulevoj moshchnosti ZPR-III. Provodyatsya sravneniya trekh konfiguratsij teploperedachi s ispol'zovaniem udvoennogo vremeni v kachestve optimal'nogo parametra. EHffekt proizvodstva izotopa protaktiniya-233 i urana pri otnositel'no poleznom ispol'zovanii nejtronov, vozmozhnye koehffitsienty vosproizvodstva i kharakteristiki vygoraniya otsenivayutsya v svyazi s netochnostyami v yadernykh poperechnykh secheniyakh. (author)

  15. RA Research nuclear reactor, Part 1, RA reactor operation and maintenance in 1993, with comparative review for the period 1991 - 1993, Annex 3; Projekat Istrazivacki nuklearni reaktor RA - 1 Deo Pogon i odrzavanje nuklearnog reaktora RA u 1993. godini, uz uporedni pregled za period 1991 - 1993. - prilog 3

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Mikic, N; Tanaskovic, M [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1993-12-15

    RA reactor was not operated during 1993 because of the complete instrumentation exchange. Although it has been planned to exchange the complete instrumentation until the end of 1993, and to start reactor operation in the first half of 1993 this was not fulfilled because the instrumentation was not delivered until the end of 1993. Main activities during past seven years were related to construction of the emergency cooling system; repair and reconstruction of the system for handling the spent fuel and improvement of spent fuel storage conditions; exchange of the aged instrumentation. Other reactor components and systems, reactor core, primary coolant loop and gas circulation system are in good condition concerning future start-up. [Serbo-Croat] U 1993. godini reaktor nije bio u pogonu zbog zamene njegove celokupne instrumentacije. Iako je bilo planirano da se celokupna instrumentacija zameni do kraja 1993. te da reaktor pocne sa radom u prvoj polovini 1993. Ovo nije ispunjeno jer celokupna oprema nije isporucena ni do kraja 1993. godine. Osnovni zahvati koji su u proteklih sedma godina izvrseni, odnosili su se na izgradnju sistema za udesno hladjenje, rekonstrukciju sistema za rukovanje ozracenim gorivom i poboljsanje uslova za stokiranje ovog goriva, zamenu instrumentacije. Ostali sistemi reaktora, reaktorsko jezgro, primarno kolo hladjenja i sistem za cirkulaciju gasa su u dobrom stanju i mogu se nesmetano koristiti u buducem radu.

  16. Reactor Physics Development for Advanced Gas-Cooled Reactors; Recherches en Physique des Reacteurs, pour des Reacteurs Perfectionnes Refroidis par un Gaz; Razrabotka metodov v oblasti reaktornoj fiziki dlya usovershenstvovannogo reaktora s gazovym okhlazhdeniem; Progresos de la Fisica de los Reactores de Tipo Avanzado Refrigerados por Gas

    Energy Technology Data Exchange (ETDEWEB)

    Moore, J. [United Kingdom Atomic Energy Authority (United Kingdom)

    1964-04-15

    metodos de medicion de los efectos de la reactividad en APEX, HERO y AGR, y para determinar los datos relativos a la estructura fina y a la distribucion de la potencia en los conjuntos combustibles complejos. Los trabajos se concentran principalmente en el desarrollo de un metodo capaz de sustituir al 'hetrecontrol' y al 'FTD2' , para los cuerpos de reactor cuando el combustible haya alcanzado un grado de combustion considerable. La finalidad del programa experimental con la instalacion HERO es precisamente comprobar estos metodos con cuerpos complejos, inclusive con combustible que contenga plutonio. La explotacion del reactor AGR y las mediciones fisicas que se realicen con el combustible despues de la irradiacion permitiran obtener datos adicionales sobre el efecto del plutonio. (author) [Russian] Rassmatrivaetsja tshhatel'naja jeksperimental'naja i teoreticheskaja rabota, provedennaja pri konstruirovanii, stroitel'stve i vvode v jekspluataciju Uindskejlskogo usovershenstvovannogo reaktora s gazovym ohlazhdeniem i pri okazanii obshhej pomoshhi pri razrabotke usovershenstvovannogo reaktora s gazovym ohlazhdeniem (AGR) dla proizvodstva jenergii dlja grazhdanskih celej. Daetsja opisanie znachitel'nogo ob{sup e}ma rabot, kotorye byli neobhodimy dlja razrabotki prigodnyh teoreticheskih metodov rascheta: 1) raspredelenija potoka i balansa reaktivnosti v slozhnoj aktivnoj zone reaktora; 2) raspredelenija jenergii v toplive so slozhnoj geometriej i 3) vlijanija obluchenija na toplivnye cikly i raspredelenie jenergii. V kachestve vvedenija delaetsja ssylka na jeksperimental'nye dannye i teoreticheskie metody, poluchennye v rezul'tate rabot nad uranovo-magnoksovymi sistemami, i na jeksperimental'nye dannye, poluchennye v rezul'tate Sovmestnoj jeksperimental'noj programmy Britanskoj promyshlennosti (BICEP), kotorye javilis' otpravnym momentom v razrabotke teoreticheskih metodov, primenimyh k usovershenstvovannym reaktoram s gazovym ohlazhdeniem. Dlja opredelenija parametrov

  17. The Application of Various Nondestructive Testing Methods to Fuel Elements of the Orgel Type; Application des Differentes Methodes d'Essais Non Destructifs aux Elements Combustibles du Type Orgel; Primenenie razlichnykh nedestruktivnykh metodov ispytanij k toplivnym ehlementam tipa ''orgel''; Aplicacion de Distintos Metodos de Ensayo No Destructivo a los Elementos Combustibles de Tipo Orgel

    Energy Technology Data Exchange (ETDEWEB)

    Bonnet, P.; Jansen, J. [EURATOM, C.C.R., Ispra (Italy)

    1965-09-15

    podgotovka. Govoritsja o mehanicheskom stende laboratornogo tipa dlja izuchenija ispytatel'nyh kriteriev i o polupromyshlennom stende prohozhdenija trub dlja postojannogo izuchenija s registraciej defektov. Govoritsja o trudnostjah i o sredstvah dlja ih preodolenija. v. Ispytanija radiografiej. Jetot metod opisan v special'nom doklade, zdes' govoritsja lish' o rezul'tatah, poluchennyh na silovyh trubkah ili na obolochkah. g. Drugie ispytanija. Okonchatel'nye ispytanija toplivnyh jelementov mogut byt' predstavleny v dvuh gruppah: 1) ispytanija na germetichnost' po razrabotannomu Sogevym metodu ispytanija s geliem; ustrojstvo pozvoljaet izuchat' odnovremenno 4 ili '' jelementov li'o razdel'no Inverted-Question-Mark ili 3 toplivnyh jelementa; 2) obychnye opyty s radiografiej; otdel'no vnimanie udeljaetsja izucheniju svarki i dajutsja predely jeksperimental'nyh uslovij dlja poluchenija horoshego opredelenija. V zakljuchenie predlagaetsja proekt polupromyshlennoj kontrol'noj shemy s razlichnymi vozmozhnostjami verojatnyh obrabotok i sdelany opredelennye vyvody. (author)

  18. New Instruments and Principles for the Dimensional Measurement and Measurement of Spacing of Reactor Components; Nouveaux Instruments et Procedes de Mesure des Dimensions et de l'Espacement des Elements d'un Reacteur; Novye pribory i printsipy izmereniya razmerov i raspolozheniya komponentov reaktora; Nuevos Instrumentos y Principios para Medir las Dimensiones y la Separacion Entre Componentes de Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

    1965-09-15

    vihrevyh tokov dlja izmerenija tolshhiny listov i kontejnerov iz cvetnyh i austenitnyh metallov s pomoshh'ju perehodnyh katushek; b) metod vihrevyh tokov dlja izmerenija tolshhiny stenok trub s pomoshh'ju prohodnyh katushek. Opisyvajutsja prigodnye dlja jetogo pribory i ih primenenie. Izmerenie tolshhiny stenok uzlov reaktora iz cvetnyh metallov po 'metodu magnitnogo sharai . Ob'jasnjaetsja princip jetogo novogo vida izmerenij, oblast' ego primenenija (osobenno dlja tochechnyh izmerenij) i opisyvaetsja primenjaemyj na praktike pribor. Izmerenie materialov nemagnitnyh pokrytij na magnitnoj osnove. Ob'jasnjajutsja principy izmerenij (metody magnitnogo polja postojannogo toka i peremennogo toka) i opisyvajutsja pribory dlja izmerenija nemagnitnyh pokrytij tolshhinoj ot 3 mikron do 20 mm. Osobo rassmatrivaetsja problema otlozhenija stellita na ferritnyh stenkah korpusov reaktorov. Izmerenie pokrytij, neprovodjashhih jelektrichestvo,-na materialah iz cvetnyh metallov. Ob'jasnjaetsja princip takogo izmerenija (vihrevye toki). Opisyvaetsja pribor dlja .takih izmerenij i tipichnye primery izmerenij. Privodjatsja beskontaktnye tehnologicheskie izmerenija fizicheskih razmerov metallicheskih komponentov reaktora. Ob{sup j}asnjajutsja razlichnye metody izmerenija chernyh i cvetnyh metallov (metod magnitnogo polja postojannogo toka i peremennogo toka, metody vihrevyh tokov). Opisyvajutsja pribory i primery distancionnogo izmerenija diametra oval'nosti, iskazhenija i t.d. komponentov reaktora. Opisyvajutsja metody opredelenija raspolozhenija takih komponentov v 'gorjachej' zone reaktora. ' Opisyvaetsja pribor dlja registracii profilja poverhnosti i neposredstvennogo opredelenija haraktera nerovnosti (''Rauhtiefe'', ''Glaettungstiefe'', GLA value i RMS value). Rassmatrivajutsja tipichnye primery ispol'zovanija jetogo pribora opredelenija nerovnostej komponentov reaktora. Osoboe vnimanie udeljaetsja vozmozhnosti ispol'zovanija nebol'shogo universal'nogo datchika v ''gorjachih'' zonah i

  19. Measurements at the RA Reactor related to the VISA-2 project - Part 3, calculation of VISA-2 samples influence on the reactor reactivity, on the depression of thermal neutron flux in VK-5 channel and VISA-2 samples; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - III deo, Proracun uticaja uzoraka VISA-2 na reaktivnost reaktora, na depresiju fluksa termalnih neuntrona u kanalu VK-5 i u uzorcima VISA-2

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-01

    The objective of this task was to determine the thermal neutron flux in the RA reactor cell with VISA-2 samples, the influence of VISA-2 samples on the thermal neutron flux distribution in the vicinity of VK-5 channel and the antireactivity of VISA-2 samples placed in the RA reactor core. This distribution is needed for calculating the mean value of absorption and thermal efficiency factor in the reactor cell with the sample. Thermal neutron flux distribution without the sample was calculated by diffusion theory. Fast neutron flux space distribution was assumed to be constant, i.e. that it is dependent only on the nuclear properties of the materials. Macroscopic thermal neutron flux distribution was determined by two-group diffusion theory using the four factor formula applied for two regions: active RA region, and reactor region with calls containing VISA-2 samples. This calculation enables estimation of the VISA-2 samples influence on the thermal neutron flux distribution in the VK-5 channel. Antireactivity of VISA-2 samples was calculated by neutron diffusion theory applying the perturbation method. [Serbo-Croat] Cilj ovog zadatka je da se odredi raspodela fluksa termalnih neutrona u celiji reaktora RA sa uzorcima VISA-2, uticaj uzoraka VISA-2 na makroskopsku raspodelu termalnih neutrona u blizini uzoraka, tj. u kanalu VK-5, kao i antiraktivnost uzoraka VISA-2 ubacenih u jezgro RA. Poznavanje ove raspodele potrebno je za izracunavanje srednje apsorpcije i faktora termalnog iskoriscenja u celiji reaktora sa uzorkom. Raspodela fluksa termalnih neutrona u celiji RA bez uzorka izracunata je na bazi difuzione teorije. Fluks brzih neutrona uzet je kao konstanta s obzirom na prostorne koordinate, tj. da zavisi samo od nuklearnih karakteristika materijala. Makroskopska raspodela fluksa termalnih neutrona u okolini VISA-2 odredjena je na bazi dvogrupne difuzione teorije preko formule cetiri faktora, primenjene na dve zone: prva aktivna zona RA, i druga reaktorka sredina

  20. Analiza poluprovodničkih kvantnih generatora tipa A3B5 po nano nivoima / Analysis of semiconductor quantum generators of A3B5 type at nano levels / Наноуровневый анализ полупроводниковых квантовых генераторов типа A3B5

    Directory of Open Access Journals (Sweden)

    Leonid I. Grečihin

    2015-04-01

    Full Text Available U članku se obrazlaže formiranje klasterne rešetkaste strukture poluprovodničkog kristala tipa A3B5. Predstavljen je način deformacije elektronskih opni atoma koji su u sastavu elemenata poluprovodničke kristalne strukture. Na primeru kristala iz jedinjenja indijuma i elemenata pete grupe Mendeljejeve tablice, utvrđeno je među kakvim energetskim nivoima dolazi do generisanja poluprovodničkog kvantnog generatora. Definisani su tehnološki uslovi za izradnju lasera tipa A3B5. / The article describes the formation of the cluster grid structure of semiconductor crystals of A3B5 type. The deformation of the electron shells of the atoms in semiconductor crystal structure elements has been presented. Crystals of the Indium compounds and the elements from Group 5 of the Mendeleev periodic table have been used to show the energy levels where a semiconductor quantum generator is generated. The technological conditions for an A3B5 type laser realisation have been defined. / Обосновано образование кластерной решеточной структуры полупроводниковых кристаллов типа А3В5. Показано, каким образом происходит деформация электронных оболочек атомов составных элементов полупроводниковой кристаллической структуры. На примере кристаллов из соединений индия с элементами пятой группы таблицы Менделеева установлено, между какими энергетическими уровнями реализуется генерация полу- проводникового квантового генератора. Сформулированы тре бования к технологии изготовления лазеров на основе А3В5.

  1. Industrial Ultrasonic Inspection of Stainless-Steel Claddings for the EL4 Reactor; Controle Industriel par Ultrasons des Gaines en Acier Inoxydable du Reacteur EL4; Promyshlennyj kontrol' obolochechnykh trub iz nerzhaveyushchej stali reaktora dlya EL4 s pomoshch'yu ul'trazvukovogo metoda; Metodos Ultrasonicos para Control Industrial de las Vainas de Acero Inoxidable del Reactor EL4

    Energy Technology Data Exchange (ETDEWEB)

    Prot, A. C.; Foulquoer, H. E.; Peyrot, J. P. [Centre d' Etudes Nucleaires de Saclay (France)

    1965-09-15

    'nosti reaktorov. Podtverzhdaetsja, chto vybor metoda, kotoryj sleduet primenjat' i razrabatyvat', javljaetsja trudnym. Privodjatsja osnovnye momenty. Posle togo, kak v rezul'tate laboratornyh rabot sdelan vybor, voznikajut dve novye problemy: D) vnedrenie v promyshlennost' neobhodimost' ucheta dopustimogo kachestva v opredelennyj moment metodami izgotovlenija v svjazi s ustanovlennymi bolee ili menee proizvol'nym obrazom normami dlja priema. Jeto, v dejstvitel'nosti, obuslavlivaetsja neobhodimost'ju v statisticheskom issledovanii komplektov trub razlichnogo izgotovlenija i ih klassifikacii po otnosheniju k bolee ili menee strogim normam. Vidno, chto kolichestvo podlezhashhih kontrolju trub znachitel'no prevyshaet pervonachal'no namechennoe. Jeto vedet k izucheniju avtomaticheskogo kontrol'nogo mehanizma, sposobnogo udovletvorit' odnovremenno i trebovanijam tempa, i trebovanijam, vytekajushhim iz vybrannogo tipa kontrolja: poslednie obychno svodjatsja k mehanicheskomu kontrolju i nuzhdajutsja v osobenno tshhatel'no razrabotannoj konstrukcii. Sovokupnost' jetih soobrazhenij privela k razrabotke ustrojstva, temp raboty kotorogo uzhe sejchas mozhet bez truda pokryt' potrebnosti vsego cikla proizvodstva toplivnyh jelementov. Vozmozhnosti jetogo ustrojstva tesno svjazany s harakteristikami podobrannogo oborudovanija navedenija i kontrolja, v osobennosti so svojstvami jelektroniki priborov kontrolja po ul'trazvuku i so svojstvami ispol'zuemyh preobrazovatelej. K tomu zhe iz jetogo issledovanija javstvuet, chto standartnoe oborudovanie daleko ne sootvetstvuet probleme i chto uzhe sejchas sleduet predusmotret' osoboe ustrojstvo dlja dannogo tipa kontrolja. (author)

  2. The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Huddle, R. A.U.; Shepherd, L. R. [Organization for Economic Co-Operation and Development, Dragon Project, Atomic Energy Establishment, Winfrith, Dorset (United Kingdom)

    1963-11-15

    comportamiento de estos materiales en condiciones de funcionamiento normales. Se comunican los resultados de las investigaciones sobre irradiacion, asi como de los trabajos efectuados en los circuitos del reactor. El objetivo principal de este programa es el perfeccionamiento de los reactores de elevada temperatura refrigerados por gas para aplicarlos a la generacion de electricidad en condiciones rentables. (author) [Russian] Proekt vysokotemperaturnogo reaktora (DRAGON)sozdan dlya razrabotki tekhnologii vysokotemperaturnykh reaktorov s gazovym okhladitelem; v nem predusmatrivalos' sooruzhenie i ehkspluatatsiya opytnogo reaktora na 20 mgvt (tepl.). Reaktor, sooruzhenie kotorogo budet vskore zakoncheno, predstavlyaet soboj sistemu, okhlazhdaemuyu geliem; temperatura na vykhode iz aktivnoj zony budet dostigat' 750{sup o}C. V nem budet ispol'zovat'sya U-235 v kachestve goryuchego i torij v kachestve vosproizvodyashchego materiala. Kharakternoj osobennost'yu sistemy yavlyaetsya otsutstvie kakogo-libo metalla v aktivnoj zone. Vvidu togo, chto v reaktore dolzhny razvivat'sya ves'ma vysokie temperatury,' a imenno, 1050{sup o}C na poverkhnosti teplovydelyayushchego ehlementa i do 1500{sup o}C v naibolee sil'no nagrevaemykh tochkakh topliva, dlya ego sooruzheniya ispol'zovany ogneupornye nemetallicheskie materialy. Vse veshchestvo aktivnoj zony sosredotocheno v teplovydelyayushchem ehlemente, blagodarya chemu sootnoshenie mezhdu poverkhnost'yu teploperedachi i ob{sup e}mom aktivnoj zony dostigaet bol'shogo znacheniya, i, sledovatel'no, pozvolyaet dostigat' vysokoj srednej plotnosti ehnergii v sravnitel'no kompaktnoj sisteme. Kazhdyj teplovydelyayushchij ehlement sostoit ieh gruppy grafitovykh trubok, zapolnennykh grafitovymi tabletkami, soderzhashchimi rasshcheplyayushcheesya i vosproizvodyashchee veshchestva v vide karbidov. Gelievyj okhladitel' prokhodit po osi. kazhdogo teplovydelyayushchego sterzhnya i vyvoditsya u ego osnovaniya, okhladitel' zatem napravlyaetsya v ochistitel

  3. Effektivnost' Amarila u bol'nykh sakharnym diabetom tipa 2, ozhireniem i arterial'noy gipertoniey

    Directory of Open Access Journals (Sweden)

    V B Mychka

    2002-12-01

    Full Text Available Сахарный диабет (СД типа 2 представляет серьезную медицинскую и социальную проблему. Связан о это с чрезвычайно высокой распространенностью СД типа 2 и высоким риском развития сердечно-сосудистых осложнений, ранней инвалидизацией больных и преждевременной смертностью. В России 8 млн человек, или 5% населения, страдает СД. Смертность больных СД в 2.3 раза выше, чем в популяции. Среди больных, страдающих СД, распространенность ИБС в 2-4 раза, риск развития инфаркта миокарда ? в 6-10 раз и мозговых инсультов ? в 4-7 раз выше, чем среди лиц без СД. Артериальной гипертонией страдает почти 80% больных СД 2 и у этой категории больных на 1/3 снижена продолжительность жизни. Артериальная гипертония может быть как следствием, так и причиной развития СД. Оба эти заболевания взаимно усугубляют тяжесть течения, и тем самым повышается риск поражения органов-мишеней.

  4. Osobennosti kliniki i diagnostiki ishemicheskoy nefropatii u bol'nykh sakharnym diabetom 2 tipa

    Directory of Open Access Journals (Sweden)

    Inna Igorevna Klefortova

    2007-12-01

    Full Text Available Цель. Оценка распространенности особенностей клинического течения и прогностической значимости ИН у больных сахарным диабетом 2 типа. Материалы и методы. В скрининговое исследование были включены 157 пациентов (63 мужчины, 94 женщины с СД 2 в возрасте старше 50 лет. Всем пациентам проводилось общеклиническое обследование: клинический анализ крови, общий анализ мочи, биохимическое исследование крови, коагулограмма, оценка углеводного обмена (гликированный гемоглобин, альбуминурия, скорость клубочковой фильтрации (СКФ, ЭКГ, суточное мониторирование АД, ЭХОКГ, осмотр глазного дна. Всем пациентам была выполнена дуплексная ультрасонография ПА и брюшной аорты аппаратом. Для верификации диагноза ИН выполнялась магнитно резонансная ангиография (МРА ПА и брюшной аорты с внутривенным введением контрастного препарата. Результаты. Выявлено 58 (36,3% пациентов с СД 2 со стенозом ПА, из них: у 47 (28,7% пациентов ? односторонний, у 11 (7,6 % ? двусторонний. Оценивая возрастное распределение ИН, было отмечено, что чаще всего стеноз ПА определялся в возрастной группе от 50 до 59 лет ? 41,3%, в группе 60?69 лет этот показатель составил 30,7%, у пациентов старше 70 лет ? 40,9%. При сравнении значений уровня креатинина и СКФ до и после МРА и МСКТ статистически значимых различий получено не было. Оба метода визуализации позволили безопасно верифицировать диагноз у больных СД 2 с СКФ >30 мл/мин/1,73м2. Заключение. Дуплексная сонография ПА и брюшной аорты может служить методом скрининга ИН у больных СД 2. МРА и МСКТ являются безопасными методами верификации диагноза при условии соблюдения профилактики контрастиндуцированной нефропатии у больных СД 2. ИН является фактором риска прогрессирования кардиальной и почечной патологии у больных СД 2.

  5. Medikamentoznaya terapiya ishemii nizhnikh konechnostey u bol'nykh sakharnym diabetom 2 tipa

    Directory of Open Access Journals (Sweden)

    Alla Yur'evna Tokmakova

    1999-03-01

    Full Text Available Актуальность. Наряду со столь высокой распространенностью СД 2 является и одной из основных причин ранней инвалидизации и смертности больных трудоспособного возраста. Данная категория пациентов имеет повышенный риск ампутации нижних конечностей по поводу гангрены, развившейся на фоне артериальной и венозной недостаточности. Это обусловливает актуальность комплексной терапии больных СД 2, включающих, помимо компенсации углеводного обмена, использование различных медикаментозных средств, улучшающих артериальный и венозный кровоток. Применение гликозаминогликанов является одним из основных компонентов современного лечения этой большой группы больных. Цель. Целью данного исследования была оценка влияния Вессел Дуэ Ф на состояние магистрального кровотока в артериях нижних конечностей, липидный обмен и состояние свертывающей системы крови у больных СД 2, имеющих ишемическую форму поражения стоп и голеней. Материалы и методы. В исследование были включены 30 больных сахарным диабетом 2 типа. В ходе исследования оценивали: уровень компенсации углеводного обмена по содержанию гликированного гемоглобина (HbA1с, индекс массы тела, уровень систолического и диастолического артериального давления в плечевой артерии, показатели липидного спектра сыворотки крови, состояние системы гемостаза по данным тромбоэластографии и показателям протромбинового (ПТВ, тромбинового, активированного частичного тромбопластинового времени. Терапия препаратом Вессел Дуэ Ф велась по следующей схеме: 600 единиц внутримышечно 1 раз в сутки в течение 10 дней без перерывов на выходные дни, затем по 500 ЕВЛ (2 капсулы перорально 1 раз в сутки в течение 72 дней. Эффективность лечения оценивалась через 2, 8 и 12 нед от начала лечения. Лечение сахарного диабета проводилось как с помощью инсулинотерапии (55,6%, так и пероральными сахароснижаюшими препаратами (40,7%; один больной получат только диетотерапию. Результаты. Результаты проведенного обследования позволили диагностировать у больных ишемическую форму поражения нижних конечностей, протекающую на фоне удовлетворительной компенсации сахарного диабета и проявляющуюся как субъективно, так и при проведении лабораторных и инструментальных тестов. Уже через 2 недели от начала терапии все больные отметили уменьшение интенсивности перемежающейся хромоты. Это подтвердилось при провдении тредмил-тест а и допплерографического исследования. Через 8 недель лечения положительная динамика в клинической картине стала более отчетливой: про должало увеличиваться расстояние безболевой ходьбы (до 115+7 м, увеличились средняя скорость кровотока и линейна я скорость кровотока. Выводы. Применение препарата Вессел Дуэ Ф позволяет значительно уменьшить интенсивность перемежающейся хромоты у всех больных с ишемической формой поражения нижних конечностей. В случае выраженного болевого синдрома целесообразно назначать препарат в дозе 600 ЕВЛ внутримышечно в течение 10-14 дней с последующим продолжением лечения путем перорального приема препарата в дозе 500 ЕВЛ в сутки в течение 70-80 дней. Препарат оказывает стойкое положительное влияние на показатели периферического артериального кровотока, что выражается в нормализации ЛПИ у всех обследованных, значительном увеличении средней скорости кровотока и скорости линейного кровотока. Вессел Дуэ Ф позволяет достичь нормокоагуляции у пациентов с исходной гиперкоагуляцией по данным тромбоэластограммы.

  6. Rezul'taty primeneniya strukturirovannoy programmy obucheniya bol'nykh sakharnym diabetom 2 tipa na insulinoterapii

    Directory of Open Access Journals (Sweden)

    Olga Georgievna Mel'nikova

    2008-12-01

    Full Text Available Цели. Оценка эффективности программы обучения для больных СД2 на инсулинотерапии по ряду показателей (HbA1c, масса тела, частота гипогликемий, показатели поведения, связанного с заболеванием. Сравнение эффективности групповой и индивидуальной форм обучения. Материалы и методы. В исследование включались больные с верифицированным диагнозом СД2, получающие терапию инсулином не менее 3 месяцев, изъявившие согласие на обследование, не имеющие терминальных стадий осложнений СД, тяжелых сопутствующих заболеваний, которые могли бы помешать обучению, а также выраженного снижения зрения или слуха. Цикл обучения в группах (по 5?7 больных в каждой состоял из 6 занятий в амбулаторном режиме (3 раза в неделю. Продолжительность одного занятия составляла 3 часа (в течение этого времени обучающим в обязательном порядке проводилась индивидуальная работа с каждым больным. Результаты. Через 6 месяцев после завершения обучающего цикла выявлено снижение уровня HbA1c в обеих группах: после обучения в группе до 7,4?1,6%, после индивидуального обучения ? до 8,1?1,1%. У 8 (8,9% пациентов из первой группы и 12 (9,5% из второй группы уровень HbA1c не превышал 7,0%. После обучения в обеих группах больных отмечена значительная динамика в отношении показателей, характеризующих поведение, связанное с заболеванием и отношение к его лечению. Выводы. Показана эффективность структурированной программы обучения для больных СД2 на инсулинотерапии в достижении гликемического контроля. Получены данные о позитивном влиянии программы на показатели поведения пациентов, связанного с заболеванием. В результате применения программы обучения не было отмечено увеличения массы тела и частоты гипогликемий, несмотря на снижение уровня гликированного гемоглобина. Показана сопоставимая эффективность программы при групповом и индивидуальном обучении больных.

  7. Generik atorvastatina Tulip? v lechenii dislipidemii u bol'nykh s sakharnym diabetom 2 tipa

    Directory of Open Access Journals (Sweden)

    Alsu Gafurovna Zalevskaya

    2007-06-01

    Full Text Available Цель. Оценка эффективности и безопасности применения нового генерика аторвастатина ? препарата Тулип (ЛЕК, Словения у больных СД 2 типа и дислипидемией. Материалы и методы. В открытое проспективное контролируемое исследование эффекта препарата Тулип были включены 20 пациентов. Для сравнения была выбрана группа пациентов (n=20, сопоставимая по демографическим характеристикам, также не получавшая ранее терапию липидснижающими препаратами. Протокол обследования включал стандартный опрос, осмотр, антропометрическое обследование. Лабораторные исследования проводили в сыворотке венозной крови, взятой утром натощак после 12-часового голодания. Для оценки степени компенсации СД определяли уровни холестерина, ЛПНП, ЛПВП, триглицеридов, АЛТ, АСТ в сыворотке (визит 1?3. Уровни HbA1c, холестерина, ЛПНП, ЛПВП, триглицеридов исследовали и в конце наблюдения. Результаты. В основной группе за время наблюдения обнаружено снижение уровня ЛПНП. Увеличение дозы препарата Тулип до 20 мг/день требовалось 9 пациентам. Все больные этой группы отмечали хорошую переносимость препарата. Выводы. Генерик аторвастатина Тулип? Лек, Словения, является эффективным препаратом с высоким уровнем без опасности для лечения дислипидемии у пациентов с СД 2 типа. Улучшение гликемического профиля у больных СД 2 типа не сопровождается спонтанной нормализацией липидного спектра и требует медикаментозной коррекции нарушений липидного обмена.

  8. New Methods and Facilities for the Measurement of Physical Properties of Reactor Components and Irradiated Materials; Nouveaux Procedes et Instruments de Mesure des Proprietes Physiques des Elements de Reacteur et des Matieres Irradiees; Novye metody i sredstva izmereniya fizicheskikh s vojstv komponentov reaktora i obluchennykh materialov; Nuevos Metodos y Equipos para Medir Propiedades Fisicas de Componentes de Reactor y de Materiales Irradiados

    Energy Technology Data Exchange (ETDEWEB)

    Foerster, F.; Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

    1965-09-15

    kolebanija ili putem izmerenija polushiriny rezonansnoj krivoj. Privodjatsja primery izmerenij vosstanovlenija posle radiacionnogo.povrezhdenija i posle plasticheskoj deformacii, a takzhe primery stepeni gra- fitizacii. Opisyvajutsja obnaruzhenie defektov i kolebanija plotnosti grafitovyh blokov. Krome togo ob{sup j}asnjaetsja metod issledovanija zakreplenija tabletok iz UO{sub 2} v tonkostennyh austenitnyh trubkah. Opisyvaetsja special'naja pech' dlja izuchenija uprugogo i neuprugogo povedenija ''gorjachih'' obrazcov pri temperaturah ot 20 do 1000 Degree-Sign C. Obsuzhdaetsja kontrol' kachestva cvetnyh metallov putem izmerenija jelektroprovodnosti s pomoshh'ju vihrevyh tokov. Opisyvaetsja pribor dlja beskontaktnogo izmerenija jelektroprovodnosti cvetnyh metallov. Ob'jasnjaetsja sootnoshenie mezhdu jelektroprovodnost'ju i deformaciej pod naprjazheniem cvetnyh metallov i splavov. Osoboe vnimanie obrashhaetsja na izmerenie nebol'shih po razmeru obrazcov. Opisyvaetsja ustrojstvo dlja distancionnyh prjamyh izmerenij v ''gorjachej'' zone reaktora. Rassmatrivaetsja zavisimost' jelektroprovodnosti ot doz obluchenija. Opisyvaetsja pribor dlja izmerenija pronicaemosti, ostatochnoj magnitnoj indukcii i kojercitivnoj sily kak funkcii mehanicheskogo naprjazhenija, uprugoj i plasticheskoj deformacii i doz obluchenija. Opisyvajutsja izmerenija izmenenij magnitnyh svojstv kak funkcii uprugogo naprjazhenija i plasticheskoj deformacii. Rassmatrivaetsja vlijanie obluchenija na pronicaemost' i kojercitivnuju silu. Opisyvaetsja pribor dlja bystrogo izmerenija i neposredstvennogo opredelenija pronicaemosti komponentov iz nerzhavejushhej stali. Ob'jasnjaetsja sootnoshenie mezhdu pronicaemost'ju i soderzhaniem D ferrita. Rassmatrivajutsja rezul'taty izmerenij procentnogo soderzhanija D ferrita v svarnyh shvah trubok iz nerzhavejushhej stali i izmerenij osazhdenija D ferrita kak funkcii plasticheskoj deformacii (svobodnaja kovka toplivnyh jelementov reaktora). (author)

  9. The Problems of Controlling Defects in the Materials Used for the First Czechoslovak Nuclear-Power Station; Problemes de Controle des Defauts dans les Materiaux Utilises a la Premiere Centrale Nucleaire de Tchecoslovaquie; Problemy defektoskopicheskogo kontrolya stroitel'nykh materialov reaktora pervoj chekhoslovatskoj atomnoj ehlektrostantsii; Problemas de Control de Defectos en los Materiales Utilizados en la Primera Central Nuclear de Checoslovaquia

    Energy Technology Data Exchange (ETDEWEB)

    Radislav, Filipp [Zavody Im.V.I. Lenina, Pl' zen, Czechoslovakia (Czech Republic)

    1965-09-15

    . Igualmente, se compensa el efecto de la irregularidad del acoplamiento acustico; el dispositivo envia impulsos al dispositivo del registro a distancia. Las dimensiones del defecto se determinan con ayuda de un atenuador. En la actualidad, se esta montando una instalacion automatica que permitira proceder al control de la superficie de un cilindro vertical. En el caso de las soldaduras, es necesario efectuar el control en la parte exterior a temperatura elevada. Con esa finalidad, en la fabrica 'V.I. Lenin' d e Pilsen se ha construido un dispositivo especial que permite procecer a controles de gran exactitud a altas temperaturas. El control no destructivo de los elementos soldados se efectua igualmente por rayos X. La medicion de pequenosi espesores y del metal base de una soldadura se hace mediante rayos X caracteristicos, utilizando chasis especiales. En la radioscopia de piezas soldadas de gran espesor se recurre a un betatron de procedencia checoslovaca. En la memoria se describe la tecnica de los ensayos, los resultados obtenidos y se comparan las caracteristicas del mencionado betatron de 15 MeV con otro construido por la firma Siemens. (author) [Russian] Daetsja kratkoe opisanie korpusa reaktora pervoj chehoslovackoj atomnoj jelektrostancii. Vysokie tre- bovanija k konstrukcii i tehnologii izgotovlenija korpusa reaktora, vypolnennogo iz nizko- legirovannoj nestarejushhej stali (tolshhina stenok 650 mm), priveli k neobhodimosti razra- botki metoda 'svidetelej' dlja kontrolja prochnosti konstrukcii bez razrushenija osnovnogo materiala i svarnyh soedinenij. Dlja kontrolja kachestva osnovnogo materiala i svarnyh soedinenij v bol'shoj mere is- pol'zuetsja ul'trazvukovoj impul'snyj metod s primeneniem odnogo zonda. Daetsja opisanie metodiki ispytanij i ocenki pokazanij vo vremja issledovanija osnovnogo materiala, a takzhe metodiki ispytanija kachestva jelektroshlakovyh svarnyh soedinenij, svarnyh soedinenij, provedennyh v atmosfere uglekislogo gaza , i ruchnyh dugovyh

  10. RA reactor operation and maintenance; Pogon i odrzavanje reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air.

  11. Oscillation characteristics of the reactor 'A'; Oscilatorne karakteristike reaktora 'A'

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Lolic, B [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1961-07-01

    In addition to good knowledge of reactor physical properties, design of the reactor oscillator demands determining of the oscillator operating points as well as oscillation reactor properties. This paper contains study of the RA reactor power changes due to oscillations in in one of the vertical experimental channels. It has been concluded that the reactor optimum operating conditions are attained when the oscillator operates at optimum points, and other parameters are determined dependent on the sensitivity of the method and reactor stability.

  12. Calibration of RB reactor power; Kalibrisanje snage reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Markovic, H; Ninkovic, M; Strugar, P; Dimitrijevic, Z; Takac, S; Stefanovic, D; Kocic, A; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1976-09-15

    The first and only calibration of RB reactor power was done in 1962, and the obtained calibration ratio was used irrespective of the lattice pitch and core configuration. Since the RB reactor is being prepared for operation at higher power levels it was indispensable to reexamine the calibration ratio, estimate its dependence on the lattice pitch, critical level of heavy water and thickness of the side reflector. It was necessary to verify the reliability of control and dosimetry instruments, and establish neutron and gamma dose dependence on reactor power. Two series of experiments were done in June 1976. First series was devoted to tests of control and dosimetry instrumentation and measurements of radiation in the RB reactor building dependent on reactor power. Second series covered measurement of thermal and epithermal neuron fluxes in the reactor core and calculation of reactor power. Four different reactor cores were chosen for these experiments. Reactor pitches were 8, 8{radical}2, and 16 cm with 40, 52 and 82 fuel channels containing 2% enriched fuel. Obtained results and analysis of these results are presented in this document with conclusions related to reactor safe operation.

  13. Chemical dosimetry at the RA reactor; Hemijska dozimetrija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Gal, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This report presents the results of measurements of absorbed doses axial and radial distribution in the vertical experimental channels of the RA reactor. Measurements were done in channels VK-5, VK-7, VK-9 and GF-36. Results were compared to the results of calorimetry measurements and measured neutron flux values performed by other laboratories. Fricke and oxalate dosemeters were used in addition to the cobalt indicators.

  14. RB reactor noise analysis; Analiza sumova reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Velickovic, Lj; Markovic, V; Jovanovic, S [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Statistical fluctuations of reactivity represent reactor noise. Analysis of reactor noise enables determining a series of reactor kinetic parameters. Fluctuations of power was measured by ionization chamber placed next to the tank of the RB reactor. The signal was digitized by an analog-digital converter. After calculation of the mean power, 3000 data obtained by sampling were analysed.

  15. Dosimetry system of the RB reactor; Dozimetarski sistem reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Lolic, B; Vukadin, D [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1962-07-01

    Although RB reactor is operated at very low power levels, safety and dosimetry systems have high importance. This paper shows detailed dosimetry system with fundamental typical components. Estimated radiation doses dependent on reactor power are given at some characteristic points in the rooms nearby reactor.

  16. Development of Non-Metallic Fuel Elements for a High-Temperature Gas-Cooled Reactor; Mise au point d'elements combustibles non metalliques pour un reacteur a haute temperature, refroidi par un gaz; Razrabotka nemetallicheskikh teplovydelyashchikh ehlementov dlya vysokotemperaturnogo reaktora s gazovym okhlazhdeniem; Elementos combustibles no metalicos para un reactor de temperatura elevada refrigerado por gas

    Energy Technology Data Exchange (ETDEWEB)

    Liebmann, B.; Schafer, L.; Spener, G. [NUKEM, Nuklear-Chemie und -Metallurgie G.m.b.H., Wolfgang bei Hanau, Federal Republic of Germany (Germany)

    1963-11-15

    destinados al reactor de alta temperatura refrigerado por gas de la Brown-Boveri/Krupp Reaktorbau GmbH, se investigaron y desarrollaron dos conceptos de elemento combustible. El elemento consiste en ambos casos en una esfera de grafito de 6 cm de diametro que encierra una pastilla cilindrica de combustible de unos 20 mm de diametro y 16 mm de altura. La diferencia entre ambos conceptos estriba en el tipo de combustible y en la forma de preparar las esferas de grafito. En el primero, el combustible se prepara mezclando U{sub 3}O{sub 8} y grafito, prensando esta mezcla en pastillas y haciendo que ambos componentes reaccionen en un horno al vacio a 1800{sup o}C. La razon atomica U : C es 1:45. Como este tipo de pastilla combustible no retiene cuantitativamente los productos de fision, fue necesario impregnar la esfera de grafito para hacerla impermeable y mejorar su poder de retencion. De este modo, se lograron permeabilidades del orden de 10{sup -6}cm{sup 2}/s . Con arreglo al segundo concepto, el combustible consiste en una solucion solida de UC en ZrC recubierta de una capa de ZrC. La razon molar UC : ZrC asciende a 1 : 20. La pastilla combustible se preparo del modo siguiente: se mezclaron UO{sub 2}, ZrO{sub 2} y grafito y se prensaron en pastillas que se hicieron reaccionar para obtener los carburos, que a su vez se trituraron en un molino de bolas, para volver a prensarse a 2000{sup o}C. De este modo, se alcanzaron densidades superiores al 95% del valor teorico. La memoria describe en detalle la preparacion y algunas de las propiedades fisicas de las pastillas combustibles. Se espera que este tipo de combustible retenga suficientemente los gases de fision y permita el empleo de esferas de grafito no impregnadas. La memoria examina tambien otras ventajas de esos combustibles. [Russian] V svyazi s rabotami po sovershenstvovaniyu seplovydelyayushchikh ehlementov dlya vysokotemperaturnogo reaktora s gazovym okhlazhdeniem ''Obshchestvom stroitel'stva reaktorov Braun- Boveri

  17. Ultrasonic Water-Gap Measurements in MTR Fuel Elements; Mesure par Ultrasons des Espaces Intercalaires dans les Elements Combustibles des Reacteurs d'Essai de Materiaux; Izmereniya vodyanogo zazora v teplovydelyayushchikh ehlementakh dlya materialovedcheskogo reaktora s pomoshch'yu ul'trazvuka; Medicion Ultrasonica de la Capa de Agua en Elementos Combustibles para Reactores de Ensayo de Materiales

    Energy Technology Data Exchange (ETDEWEB)

    Deknock, R. [Metallurgy Department, S.C.K./C.E.N., Mol (Belgium)

    1965-10-15

    en un convertidor tiempo-tension con circuitos logicos transistorizados. El instrumento permite un ajuste continuo del cero para cualquier espesor-arbitrario de la capa de agua entre 2 y 4 mm, con lo cual posibilita un registro con el cero en el centro de la escala. Ademas, cualquier intervalo deseado de 100 {mu}m puede dar una tension estable de 1 V a la salida para accionar un registrador. Se puede medir facilmente cualquier variacion en el espesor del agua con una precision de 5 {mu}m. Se han medido con este metodo varios elementos combustibles, y los resultados y la reproducibilidad fueron muy satisfactorios. (author) [Russian] Sil'nye potoki teplo- vyh nejtronov, kotorye obychno voznikajut v novejshih reaktorah dlja ispytanija materialov, javljajutsja podhodjashhim s r e d s t v om ravnomernoj teploperedachi i nadezhnogo otvoda tepla, s pomoshh'ju kotorogo mozhno izbezhat' obrazovanija para v bol'shih ob{sup e}mah. Krome togo, v celjah kontrolja nad obshhim raspuhaniem i povedeniem reaktornogo topli- va izmerjajut vodjanoj zazor pri jeksperimentah posle obluchenija s otrabotannymi teplovy- deljajushhimi jelementami. S jetoj cel'ju byl razrabotan zond dlja izmerenija 3 - m m vodjanogo zazora teplovydeljaju- shhego jelementa ispytatel'nogo reaktora BR-2 dlinoj bolee 1 m , v osnovu kotorogo polozhen princip ul'trazvuka. Pri jeksperimentah posle obluchenija izmeritel'nyj zond dolzhen dej- stvovat' v teplovydeljajushhem jelemente, pogruzhennom v bassejn na glubinu ne menee 6 m . Zond mozhet vyderzhat' pogruzhenie v vodu prodolzhitel'nyj period vremeni, i on ne podver- gaetsja vozdejstviju obychnyh doz gamma-obluchenija. Hotja sistema dejstvuet na osnove obychnogo metoda otrazhenija impul'sov, ona pozvo- ljaet razdeljat' ispuskaemye i otrazhennye impul'sy s pomoshh'ju 10 Mgc ferrojelektriches- kogo kristalla, kotoromu svojstvenno bol'shoe rassejanie jenergii. Mozhno ispol'zovat' zapis' pokazanij oscilloskopa, v kotorom vremja registriruetsja na gorizontal'noj osi

  18. Võbor tipa svobodnoi zonõ v Estonii = The choice of the free zone model in Estonia / Jana Tshernjavskaja

    Index Scriptorium Estoniae

    Tshernjavskaja, Jana

    2004-01-01

    Tollivabatsooni mõistest ja ülesannetest vastavalt Euroopa Liidu tollikoodeksile. Eestis tegutsevate vabatsoonide (Muuga, Sillamäe, Valga) vastavusse viimisest EL-i vabakaubanduspiirkondade tüüpidega

  19. Nuclear fuel burnup calculation in a Voronezh type reactor; Analiza izgaranja nuklearnog goriva u reaktoru tipa Voronjez

    Energy Technology Data Exchange (ETDEWEB)

    Matausek, M; Marinkovic, N; Kocic, A [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1977-07-01

    In order to summarize and present our abilities to perform a complex computation of the nuclear fuel burn-up, a systematic review of the available methods, algorithms and computer programmes is given in this paper. The computer programmes quoted have all been developed, modified and tested in our department, so that they can be successfully used in the analysis of nuclear power plants from both physics and economic points of view. For a commercially proven nuclear reactor - reactor of the Voronezh type - an illustrative computation of the fuel burn-up is performed. The typical results are presented and discussed. The conclusion concerns the completion of a modular scheme for the fuel burn-up calculation and the fuel cycle analysis (author)

  20. Vliyanie T-aktivina na pokazateli kletochnogo zvena immuniteta u bol'nykh s vpervye vyyavlennym sakharnym diabetom 1 tipa

    Directory of Open Access Journals (Sweden)

    V I Novikov

    1999-12-01

    Full Text Available Актуальность. К настоящему времени получены положительные экспериментально-клинические результаты при применении никотинамида, циклоспорина А в дебюте СД. Одним из методов воздействия на течение иммунологических процессов при СД 1 типа может быть неселективная иммунотерапия и, в частности, использование пептидов тимуса. Цель. Изучение влияния Т-активина на некоторые показатели клеточного звена иммунитета у больных с впервые выявленным СД. Материалы и методы Клинико-иммунологическое обследование было проведено 21 больному с впервые выявленным СД 1 типа. Диагноз диабета основывался на данных клинической картины, метаболических показателей (гликемия, HbA1c, кетонурия, показателей базального и стимулированного уровня С-пептида. Показатели клеточного звена иммунитета оценивали методом непрямой иммунофлуоресценции с использованием монокльнальных антител. Статистическую обработку данных проводили с использованием непараметрических методов анализа. Результаты. У всех больных не выявлено изменений относительного содержания общих Т-лимфоцитов (CD3 в крови. При изучении содержания В-лимфоцитов в крови нормальные значения были у 16 из 21 больного. У 5 больных выявлено повышение содержания npeB-(CD19+ и В-лимфоцитов (CD20+. Наиболее выраженные изменения отмечены в содержании активированных лимфоцитов. Экспрессия CD95+ выявлена у 13 больных СД (62%. Наиболее существенное влияние Т-активин оказал на содержание CD23+, CD71+, CD95+, которое снизилось, в среднем в 2,5-3 раза, а экспрессия CDDR+ - на 20%.Выводы. Результаты исследования свидетельствуют о нормализующем влиянии Т-активина на показатели клеточного звена иммунитета у больных с впервые выявленным СД.

  1. Korrektsiya arterial'noy gipertonii u bol'nykh sakharnym diabetom 2 tipa: fokus na zhestkost' arteriy

    Directory of Open Access Journals (Sweden)

    2011-06-01

    Full Text Available Elevation of the arterial stiffness is one of the important pathogenic factors associated with a high risk of cardiovascular complications and mortality rate in patients with diabetes and metabolic syndrome. Correction of the arterial stiffness has a great value for decrease of the risk of atherosclerosis progress and organ protection. Therapy with ACE inhibitor ramipril provides not only high antihypertensive effect but also significant improvement of parameters of the arterial stiffness which indicates an additional vasoprotective effect of the drug.

  2. Dinamika klyuchevykh mediatorov insulinorezistentnosti u bol'nykh sakharnym diabetom 2 tipa pri primenenii metformina (Formin Pliva?

    Directory of Open Access Journals (Sweden)

    Mikhail Ivanovich Balabolkin

    2004-12-01

    Full Text Available Цель. Изучение влияния формина (метформина не только на состояние углеводного, но и липидного обмена, динамику содержания лептина, его растворимого рецептора и альфа-фактора некроза опухолей (альфа-ФНО в сыворотке крови у больных СД 2. Материалы и методы. Обследовано 262 больных. Общий анализ крови и мочи проводили через каждый месяц наблюдения, а биохимический анализ крови, включая содержание общего ХС, ТГ, ХС ЛПНП и ЛПОНП и ХС ЛПВП, мочевины, креатинина, печеночных ферментов, проводили на 1-м и 4-м визитах. Лечение формином проводилось в течение не менее 12 нед. и изучалось при этом его влияние на состояние углеводного и липидного обмена у больных СД 2. Из общего числа обследованных у 26 больных на фоне терапии формином изучалось содержание лептина, растворимого рецептора к лептину и альфа-ФНО. Результаты. На фоне лечения формином у больных отмечалось улучшение углеводного обмена, которое сопровождалось статистически достоверным снижением гликемии натощак. Компенсация углеводного обмена у больных также сопровождалась статистически достоверным уменьшением индекса мас? сы тела с 34,02+0,33 кг/м2 до 32,73+0,33 кг/м2. У больных на фоне лечения формином наблюдается недостоверное снижение содержания лептина, растворимого рецептора к лептину и статистически достоверное снижение альфа-ФНО в сыворотке крови. Выводы. проведенные исследования показывают, что формин обладает выраженным антигипергликемическим эффектом, способствует улучшению компенсации углеводного обмена, что сопровождается статистически достоверным снижением гликемии и уровня гликозилированного гемоглобина в сыворотке крови. Наряду с этим на фоне терапии формином отмечается снижение уровня холестерина ЛПНП и повышение содержания холестерина ЛПВП, при практически неизмененных показателях содержания общего холестерина в сыворотке крови. Кроме того, лечение формином способствует статистически достоверному снижению содержания альфа-ФНО и умеренному понижению уровня лептина и его растворимого рецептора в сыворотке крови.

  3. Detsko-roditel'skie otnosheniya v sem'yakh detey, bol'nykh sakharnym diabetom 1 tipa

    Directory of Open Access Journals (Sweden)

    Oleg Gennad'evich Motovilin

    2008-12-01

    Full Text Available Цель. Целью настоящего исследования явилось выявление особенностей детско-родительских отношений в семьях детей, больных СД, и изучения связи этих отношений с компенсацией заболевания. Материалы и методы. Для изучения особенностей отношений родителей к ребенку применялся опросник ?Анализ семейных взаимоотношений? Э.Г. Эйдемиллера. В исследовании приняли участие 105 детей в возрасте от 6 до 17 лет, болеющих СД 1 не менее 3 месяцев, и их матери. Результаты. Во второй группе средние значения по большинству шкал оказались несколько выше, чем в первой. Поскольку повышенные значения по шкалам опросника АСВ свидетельствуют об отклонении от нормальных отношений между матерью и ребенком, можно говорить о том, что худшая компенсация диабета связана с общей неблагополучностью воспитания. Во второй группе значительно выше показатель гипопротекции (различия значимы по Т-критерию, p

  4. Oksidativnyy stress i trombotsitarno-koagulyatsionnyy gemostaz u bol'nykh sakharnym diabetom tipa 1 s diabeticheskoy nefropatiey

    Directory of Open Access Journals (Sweden)

    Yu V Nelaeva

    2003-09-01

    Full Text Available Цель. Установить клинико-патогенетическое значение изменения уровня оксида азота в мембранах тромбоцитов, активности КСО в сыворотке крови у больных СД типа 1 с диабетической нефропатией при различных клинических вариантах течения; связь оксидативного стресса в тромбоцитах с изменением их коагулоактивности. Материалы и методы. Обследовано 80 больных СД типа 1 на ранних стадиях диабетической нефропатии в состоянии субкомпенсации. В качестве группы сравнения обследованы 30 практически здоровых лиц без отягощенного семейного анамнеза по сахарному диабету. Клиническое и биохимическое обследование включало определение углеводного обмена по уровню базальной и постпрандиальной гликемии, гликированному гемоглобину, тест на микроальбуминурию. Выделяли тромбоциты, определяли активность фермента ксантиноксидазы. Продукцию NO оценивали косвенным методом по содержанию нитритов (NO2 во взвеси тромбоцитов. Оценивали тромбоцитарное звено гемостаза. Результаты. У больных СД типа 1 с нормоальбуминурией установлен достоверный рост активности ксантиноксидазы. У больных СД типа 1 установлено снижение в клеточных мембранах тромбоцитов содержания NO2 по сравнению с показателями контрольной группы. у больных СД с отсутствием микроальбуминурии (1-я группа достоверно уменьшается абсолютное количество тромбоцитов в крови по сравнению с контролем, одновременно на 23% снижается агрегационная активность этих клеток крови в сравнении с показателями контрольной группы. Анализ агрегатограмм свидетельствует о достоверном сокращении времени достижения 1/2 максимальной агрегации (1/2 МА у больных СД типа 1. У больных СД типа 1 с нормоальбуминурией имеет место гипокоагуляция, о наличии которой свидетельствует удлинение активированного времени свертывания и частичного активированного времени свертывания, при одновременной активации противосвертывающих механизмов. Выводы. Оксидативный стресс можно рассматривать как крайне неблагоприятный фактор, влияющий на сосудистый эндотелий у больных СД типа 1 с диабетической нефропатией. У больных СД типа 1 в мембранах тромбоцитов установлено достоверное снижение содержания NO2, что может играть определенную роль в патогенезе сорудистых осложнений СД посредством изменения функциональной способности тромбоцитов. Характер и выраженность нарушений тромбоцитарно-коагуляционного гемостаза у больных СД зависят от стадии диабетической нефропатии.

  5. Disfunktsiya endoteliya i narusheniya trombotsitarno-koagulyatsionnogo gemostaza v razvitii diabeticheskoy nefropatii pri sakharnom diabete 2 tipa

    Directory of Open Access Journals (Sweden)

    V I Sizikov

    2007-03-01

    Full Text Available Цель. Изучить функциональное состояние эндотелия и коагуляционно-тромбоцитарного гемостаза у больных с впервые выявленным СД 2 типа. Материалы и методы. Для исследования было сформировано 3 группы пациентов (сопоставимых по возрасту, полу, степени ожирения и АГ: 1 больные с впервые выявленным СД 2 типа с ДН на стадии МАУ (33 человека, 2 с впервые выявленным СД 2 типа без ДН (28 человек, 3 группа контроля ? лица без нарушения углеводного обмена (34 человека с ожирением и АГ I-II степени. Определялся гликированный гемоглобин, МАУ. Производилась оценка тромбоцитарного звена гемостаза. Определяли число тромбоцитов и уровень фибриногена; фактор Виллебранда (ФВ, протромбиновое отношение (ПО и время рекальцификации. Функцию эндотелия оценивали на плечевой артерии (ПА. Результаты. У больных СД 2 и ДН на стадии МАУ дисфункция эндотелия оказалась более выраженной. Концентрация HbA1c в группе с ДН была на 0,6% выше, чем в группе с СД 2 без МАУ. Выделение белка с мочой у пациентов с ДН была на 90,9% (в 11 раз выше, чем у больных с СД без ДН У больных СД выявлена отрицательная корреляция между уровнем метаболитов NO в плазме и МАУ. Выводы. У больных с впервые выявленным СД 2 ответ ПА на РГ при наличии ДН на стадии МАУ меньше, чем у больных без ДН. СД 2 характеризуется изменениями тромбоцитарно-коагуляционного гемостаза, что проявляется повышением количества тромбоцитов с увеличением их спонтанной агрегации. Тромбоцитарно-коагуляционные измененияя наиболее выражены у больных СД 2 с ДН на стадии МАУ. Уровень метаболитов NO у больных с ожирением и АГ без СД 2 типа выше, чем при СД 2. Это может указывать на снижение выработки эндотелием NO при хронической гипергликемии.

  6. Effektivnost' primeneniya preparata Vessel Due F u bol'nykh sakharnym diabetom tipa 1 i 2 s diabeticheskoy retinopatiey

    Directory of Open Access Journals (Sweden)

    Tamara Miroslavovna Milen'kaya

    2002-09-01

    Full Text Available В связи с социальной важностью борьбы со слепотой, причиной которой является диабетическая ретинопатия (ДР, офтальмологами и эндокринологами всех стран ведется поиск более совершенных методов диагностики и лечения этого серьезного заболевания. Одной из главных профилактических мер преду?преждения развития сосудистых осложнений является компенсация СД. Важным вопросом является и выявление сосудистых изменений на ранних стадиях и проведение соответствующего лечения. В последнее время появились разработки новых препаратов. В течение последних 5 лет широк о применяется сулодексид (Вессел Дуэ Ф. Цель работы ? изучение эффективности применения сулодексида у больных с диабетической ретинопатией.

  7. Design of the Small Rods Forming the Fuel Element of the First Charge of the EL4 Reactor. Cladding Problems; Etude des crayons constituant l'element combustible du premier jeu d'EL4 - probleme de la gaine; Problema pokrytiya nebol'shikh steeknej, obrazushchikh toplivnyj ehlement pervoj zagruzki reaktora EL.4; Estudio de las barras que constituyen los elementos combustibles de la primera carga del reactor EL4 - el problema de las vainas

    Energy Technology Data Exchange (ETDEWEB)

    Bailly, H.; Ringot, C.; Weisz, M. [Centre d' Etudes Nucleaires de Saclay (France)

    1963-11-15

    ) [Spanish] Las vainas de los elementos combustibles de la primera carga del reactor EL-4 son de acero inoxidable. La eleccion del grado del acero y del espesor de la vaina depende de la resistencia a la corrosion y de la resistencia mecanica que se deseen. Las tensiones y las temperaturas de funcionamiento no permiten concebir una vaina que resista durante toda la vida util del elemento combustible si no se uti liza un grado de acero muy resistente y un espesor,superior a 0,5 mm. Se admite que la vaina se adhiera al combustible por fluencia: la deformacion por juego en sentido diametral puede producir una ovalizacion y un pliegue; el juego longitudinal puede dar lugar a flexiones de la vaina. Se han realizado muchos ensayos con vainas de 0,3 a 0,4 mm de espesor para estudiar el modo de deformacion en funcion de los juegos. Para estar seguros de que no se produciran ovaliza ciones con los espesores previstos, y para mantener lo mas baja posible la temperatura en el interior de la barra es preciso eliminar completamente el juego durante la fabricacion. (author) [Russian] Dlya pervoj nagruzki toplivnogo ehlementa reaktora EL.4 ispol'zuetsya pokrytie iz nerzhaveyushchej stali. Vybor splava i tolshchiny pokrytiya svyazan s korrozionnymi i mekhanicheskimi svojstvami metalla. Rabochie napryakheniya i temperatury ne dast vozmokhnosti sproektirovat' pokrytie, stojkoe v techenie vsego sroka sluzhby toplivnogo ehlementa; dlya dostikheniya takoj tseli neobkhodimo bylo by ispol'zovat' ochen' stojkoe pokrytie tolshchinoj bolee 0,5 mm. Dopuskaetsya, chto pokrytie v protsesse spekaniya soedinyaetsya s toplivom. Diametral'noe izmenenie toplivnykh ehlementov mokhet privesti k obrazovaniyu oval'noj formy i nerovnostej; prodol'noe izmenenie sistemy toplivnykh ehlementov mokhet privesti k prodol'nomu izgibu pokrytiya. Byli provedeny mnogochislennye opyty v otnoshenii tolshchiny pokrytiya v predelakh' 0,3 - 0,4 mm s tem, chtoby vyyasnit' kharakter izmeneniya toplivnykh ehlementov v zavisimosti

  8. Research into the causes of overheating of bearings and solving the problem of further operation of a 450 kVA short break diesel-generating set at Belgrade Airport / Исследование причин перегрева подшипников и решение проблемы дальнейшей эксплуатации дизельной элетростанции типа short break мощностью 450 кВА в ГП Аэропорт Белград / Istraživanje uzroka povišenog zagrevanja ležajeva i rešavanje problema dalje eksploatacije dizel-elektroagregata tipa short break, snage 450 kVA, u JP Aerodrom Beograd

    Directory of Open Access Journals (Sweden)

    Nikola P. Žegarac

    2016-07-01

    Full Text Available The paper presents the research into the causes of increased heating in bearings and troubleshooting further exploitation of a Short Break diesel generating set with a power of 450 kVA at Belgrade Airport. The diesel engine is a type of Short Break, which means that in the event of an interruption in the electricity supply from the city network, there is a certain interruption of about 40 seconds until diesel generators start to supply electricity to the equipment and systems at Belgrade Airport. The main function of the diesel engine is to serve as a backup source power supply for devices and systems in case of limited visibility (lighting around the runway and many other devices and systems. / В данной работе представлены исследования причин перегрева подшипников и решение проблемы дальнейшей эксплуатации дизельной электростанции типа Short Break мощностью 450 кВА в ГП Аэропорт Белград. Дизельная электростанция типа Short Break в случае перебоя электроснабжения от городских сетей останется без питания в течение 40 секунд, пока системные установки Аэропорта Белград не начнут заряжаться с помощью дизельенераторов. Дизель-генератор является резервным источником электропитания устройств и систем в условиях ограниченной видимости (освещение взлётно-посадочной полосы, рулёжной дорожки и пр.. / U radu su prikazana istraživanja uzroka povišenog zagrevanja ležajeva i rešavanje problema dalje eksploatacije dizel-elektroagregata tipa Short Break, snage 450 kVA, u

  9. Comparison of nuclear reactor types of the next generation; Komparativni prikaz novih tipova reaktorskih komercijalnih postrojenja slijedece generacije

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, Z; Kastelan, M [NPP Krsko (Slovenia)

    1992-07-01

    The paper presents a comparison for a selected relevant set of parameters for different commercial nuclear reactor types at the next generation. This parameters overview could serve as the base for the semi-quantitative decision bases for the selection of the future nuclear strategy. The number of advanced reactor designs of the LWR, HWR, GCR and LMR type are presented. Even currently many of them are still on the drawing boards, the concepts and designs should be assessed in the sense of sensible approach for planning the possible future nuclear strategy. (author) Clanek predstavlja usporedbu odabranih bitnih parametara karakteristicnih za razlicite tipove energetskih nuklearnih postrojenja slijedece generacije. Prikazani pregled parametara omogucava osnov za polu kvantitativnu osnovu za odlucivanje u svrhu donosenja odluke oko odrednica buduce strategije uporabe nuklearne energije. Brojni koncepti naprednih nuklearnih reaktora tipa LWR, HWR, GCR i LMR su prezentirani. S obzirom na cinjenicu da se mnogi of prezentiranih nalaze jos uvijek na crtacim daskama projektanata, koncepti i projekti koji su iz njih proizasli zahtijevaju analizu u smislu kvalitativnog pristupa planiranja moguce buduce nuklearne startegije. (author)

  10. Regulations and instructions for RB reactor operation; Propisi i uputstva za rad reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-07-01

    This document includes regulations for reactor RB operation, behaviour and presence of staff in the reactor building; regulations for performing experiments at the RB reactor, regulations and int ructions for the reactor operators and other staff on duty. A chapter is devoted to instruction for reactor operation with the operating documentation and special duties of the operators. Regulations and instruction concerned with accidents are described with classification of accidents and evacuation plan. Annexes to this document include: the present status of the reactor; program for training the reactor operators; forms which are obligatory to be signed for any operating activity, and the certificate of the RB reactor lattice.

  11. Design characteristics of zero power fast reactor Lasta; Osnovne karakteristike brzog reaktora nulte snage Lasta

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M; Stefanovic, D; Pesic, M; Popovic, D; Nikolic, D; Antic, D; Zavaljevski, N [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1987-07-01

    The concept, purpose and preliminary design of a zero power fast reactor LASTA are described. The methods of computing the reactor core parameters and reactor kinetics are presented with the basic calculated results and analysis for one selected LASTA configuration. The nominal parameters are determined according to the selected reactor safety criteria and results of calculations. Important aspects related to the overall safety are examined in detail. (author)

  12. RA reactor exploitation, task 3.08/01; Zadatak 3.08/01 - Eksploatacija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    During 1963 the RA reactor was operated for 1852 hours at mean power of 5.7 MW (total power production was 10716 MWh). Reactor was used for irradiation according to the demand of 356 users, and 15 experiments. The reason for decreased operation in comparison with the previous year was repair of all the reactor equipment and decontamination of the heavy water system. This report contains detailed data about reactor power, reactivity changes and fuel burnup. Mean monthly usage of the reactor experimental channels as well as samples which were irradiated are part of this report.

  13. Operation and maintenance of the RA reactor; Pogon i odrzavanje reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    During 1961 the RA reactor was used for irradiation of samples for 258 users ( from which 188 from the Institute) and for 34 experiments, this means productions of 5958 MWh. The production was almost four times bigger than during previous year due to the demand of the Laboratories of the Institute. Burnup of the fuel from the first batch was about 30%. This means that the operation time could be much higher. Number of safety shut-downs was 11. The reasons were related to electrical faults, 9 occurrences, failure of the instrument for reactor period measurement, once, and failure of the pump once. This report covers state and operation data of the reactor components, control instruments, devices for reactor protection, dosimetry, heavy water system, helium system, mechanical and electrical equipment. Problems related to training of the staff and lack of personnel are mentioned as well.

  14. RB research reactor safety report; Izvestaj o sigurnsti istrazivackog reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Pesic, M; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1979-04-15

    This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document.

  15. Measurement of neutrons in the RA reactor cell; Merenje neutrona u elementarnoj celiji reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Bosevski, T [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    A special experimental device was constructed for measuring the neutron flux distribution in the RA reactor cell. This device simulated the reactor cell in order to avoid disturbance in the reactor core. It was made of an aluminium cylindrical vessel having outer diameter same as the vertical experimental channel and contained three fuel slugs. Hole was made in through the center of the fuel slugs and a copper wire was placed in the hole for measuring the thermal neutron flux distribution. It was placed in the experimental channel VK-5 in the location of highest neutron flux. Handling of samples for irradiation was quite simple.

  16. Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1968-07-01

    Direct approach to the problem is to calculate spatial distribution of fuel concentration if the reactor core directly using the condition of maximum neutron flux and comply with thermal limitations. This paper proved that the problem can be solved by applying the variational calculus, i.e. by using the maximum principle of Pontryagin. Mathematical model of reactor core is based on the two-group neutron diffusion theory with some simplifications which make it appropriate from maximum principle point of view. Here applied theory of maximum principle are suitable for application. The solution of optimum distribution of fuel concentration in the reactor core is obtained in explicit analytical form. The reactor critical dimensions are roots of a system of nonlinear equations and verification of optimum conditions can be done only for specific examples.

  17. HETERO code, heterogeneous procedure for reactor calculation; Program Hetero, heterogeni postupak proracuna reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Jovanovic, S M; Raisic, N M [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1966-11-15

    This report describes the procedure for calculating the parameters of heterogeneous reactor system taking into account the interaction between fuel elements related to established geometry. First part contains the analysis of single fuel element in a diffusion medium, and criticality condition of the reactor system described by superposition of elements interactions. the possibility of performing such analysis by determination of heterogeneous system lattice is described in the second part. Computer code HETERO with the code KETAP (calculation of criticality factor {eta}{sub n} and flux distribution) is part of this report together with the example of RB reactor square lattice.

  18. Temperature reactivity coefficient of the RA reactor; Temperaturni koeficijenat reaktivnosti reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Strugar, P; Dobrosavljevic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Temperature reactivity coefficient of the RA reactor was determined as follows. Stabilization of moderator temperature and graphite reflector was achieved in the reactor operated at power levels of 20, 100, 500, 1000, 3000 and 5000 kW. Temperature change of the moderator was achieved by changing the water flow rate in the secondary cooling system. The fuel temperature was changed simultaneously. During the measurement at each power level the temperature change was between 30 - 50 deg C. Changing the position of the automated regulator is registered during moderator temperature change, and these changes were used for determining the total reactivity change by using the calibration curves for the automated regulator. In the measured temperature range the the reactivity change was linear and it was possible to determine the total temperature coefficient.

  19. Kardioi nefroprotektivnye effekty agonista imidazolinovykh retseptorov moksonidina v lechenii arterial'noy gipertenzii u bol'nykh sakharnym diabetom 2 tipa

    Directory of Open Access Journals (Sweden)

    Alexander Sergeevich Ametov

    2004-12-01

    Full Text Available Цель. Оценка динамики морфо-функциональных параметров миокарда и МАУ на фоне гипотензивной терапии селективного агониста имидазолиновых рецепторов моксонидина (физиотенз, Solvay Pharma у пациентов с мягкой и умеренной гипертензией ассоциированной с СД 2 типа, в течение 16 нед. активного лечения. Материалы и методы. Проведено динамическое наблюдение и лечение 30 больных артериальной гипертензией, характеризующихся стойким повышением АД, требующим постоянной гипотензивной терапии и ассоциированным с СД 2 типа. Пациенты принимали пероральные сахароснижающие препараты из группы сульфаниламидов или комбинации сульфаниламидов и бигуанидов. Оценивали следующие показатели: усредненные значения систолического АД (САД и диастолического АД (ДАД за 3 временных периода: 24 ч (САД24, ДАД24, день (САДд, ДАДд и ночь (САДн, ДАДн; нагрузка давлением? по индексу времени (ИВ ? как процент величин АД выше пороговых значений: 140/90 мм рт.ст. дневное и 120/80 мм рт.ст. ночное; вариабельность АД (ВАР ? как стандартное отклонение от средней величины (день, ночь. О выраженности суточного ритма (CP АД судили по степени ночного снижения (СНС САД, рассчитанную по разнице между средними величинами САД за день и ночь, отнесенную к средним дневным величинам САД (в %. Проводилось Эхо-КГ. Для динамической оценки состояния глазного дна выполнялась прямая и обратная офтальмоскопия при расширенном зрачке через 16 нед терапии. Результаты. У большинства пациентов (71,45% хороший гипотензивный эффект был достигнут при приеме 0,4 мг моксонидина однократно в сутки; 14,38% пациентов получали моксонидин в суточной дозе 0,2 мг. Через 8 нед терапии физиотензом в половине случаев достигнуто целевое АД (50%; хороший гипотензивный ответ (снижение ДАД на 5 мм и /или САД ? на 10 мм рт. ст. отмечен в 64,8% случаев. К концу исследования частота достижения целевого АД составила 64,28%, а хорошего гипотензивного ответа ? 96,42%. Средняя по группе СНС САД составила 7,61 ?5,21 мм рт.ст. Через 16 нед терапии число пациентов с МАУ составило 25%; 58,8% от имевших МАУ исходно имели отрицательный ?микраль-тест?. У 41,2% пациентов МАУ сократилась в среднем в 2 раза. На фоне приема физиотенза в течение всего исследования пациенты сохраняли стабильный контроль гликемии. Выводы. Терапия физиотензом в течение 16 недель оказывает многоплановое корригирующее влияние на показатели суточного профиля АД: обеспечивает достоверное оптимальное снижение АД в течение суток на долгосрочной основе; достоверно нормализует индекс нагрузки давлением в дневное и ночное время. Препарат обладает выраженным кардиопротективным действием, реализующимся в снижении ИММЛЖ и толщины стенок левого желудочка, улучшении диастолической функции миокарда по данным параметров трансмитрального кровотока. Физиотенз обладает нефропротективным действием, о чем свидетельствует достоверный регресс микроальбуминурии у пациентов с начальной стадией диабетической нефропатии.

  20. Ar prūsų kalboje egzistavo lie. tekė́ti, tẽka veiksmažodžių tipas?

    Directory of Open Access Journals (Sweden)

    Erdvilas Jakulis

    2011-11-01

    Full Text Available WERE THERE IN THE OLD PRUSSIAN LANGUAGE ANY VERBS ANALOGOUS TO LITH. tekė́ti, tẽka VERBAL TYPE?SummaryThe article seeks to determine whether the Old Prussian language could have had verbs analogous to the Lithuanian type ending in -ėti in the infinitive, -a in the present tense and -ėjo in the past tense. Vytautas Mažiulis’ Prussian Etymological Dictionary directly attributes only one reconstructed verb to this type, *skelētvei, *skela ‘to owe, to be at fault’, and indirectly connects several suffixal verb forms, *peldētvei ‘to earn; to obtain’, *kabētvei ‘to hang’, *bīlet ‘to tell’ and *kalsēt ‘to ring’. The OPr. verbs under discussion, however, belong to another verbal type (with variable suffix - inf. -ī-, praes./praet. -ā-/-ē-.The tekė́ti, tẽka verbal type arose from the past tense stem, *-ē, of root verbs with the addition of thematic personal endings, i.e., a secondary stem *-i̯ā (*tekēi̯ā. The past tense stem *-ēi̯ā suffix *-ē was then introduced into the infinitive (*tekti > *tek-ē-ti. The Prussian language added plural personal endings to vowel suffixes athematically (directly after the suffix vowel, and because the first, second and third person singular usually had a zero ending – the final vowel was that of the suffix (see Kaukienė 2000b, 58 f.. Therefore there was no basis for tekė́ti, tẽka verbs to arise.Hence we may conclude that tekė́ti, tẽka verbal type is an East Baltic innovation.

  1. The TIPA shear zone (NW-Argentina): Evidence for early devonian movement verified by Sm-Nd dating of garnet and whole rock systems

    International Nuclear Information System (INIS)

    Hockenreiner, M.; Sollner, F.; Miller, H

    2001-01-01

    The Sierra de Copacabana (Catamarca province, NW Argentina) hosts in its northernmost part a large shear zone, which can be traced back to the north into the Sa. de Fiambala and to the south at least into the Sa. de Velasco. Timing of mylonitization is an important puzzle-piece in order to understand Paleozoic geotectonic processes on the western border of Gondwana (au)

  2. Vliyanie vnutrimatochnykh kontratseptivnykh sredstv na pokazateli uglevodnogo i lipidnogo obmena u zhenshchin, bol'nykh SD 1 tipa, v period perimenopauzy

    Directory of Open Access Journals (Sweden)

    Olga Rafael'evna Grigoryan

    2004-12-01

    Full Text Available Цель. Оценить влияние современных внутриматочных контрацептивных средств (нейтральных и гестагенсодержащих на показатели углеводного и липидного обмена у женщин, больных СД 1 типа, в период перименопаузы в течение 12 мес. Материалы и методы. В исследование включены 44 женщины. лет с СД 1 типа. До начала исследования пациентки были разделены на 2 группы, по 22 женщины в каждой. В группе 1А в качестве средства контрацепции использовали Т ? образную медьсодержащую ВМС; в группе 2А ? левоноргестрелсодержащую ВМС ?Мирена?. Общее клиническое обследование включало сбор анамнестических данных, общий и гинекологический осмотры. Гинекологический осмотр включал в себя: осмотр и пальпацию молочных желез; бимануальное гинекологическое исследование; осмотр шейки матки в зеркалах; мазок по Папаниколау, мазок из влагалища на флору, а также степень чистоты и др. Для оценки степени избыточной массы тела или ожирения вычислялся индекс массы тела (ИМТ. Определялось содержание холестерина, ЛПНП, ЛПОНП. Для оценки атерогенных свойств крови использовали холестериновый индекс атерогенности. Результаты. Сравнительный анализ уровня гликированного гемоглобина у женщин с СД 1 типа выявил, что в обеих группах пациенток его изменения носили достоверно не значимый характер и не было выявлено изменений в среднесуточных дозах препаратов инсулина. В обеих группах женщин, больных СД 1 типа, находящихся на внутриматочной контрацепции, и в группе контроля достоверно значимых изменений в указанном показателе в динамике выявлено не было. При сравнительном анализе показателей липидного обмена у 21 из 44 (48% женщин с СД 1 типа была выявлена гиперлипидемия IIа типа, а в контрольной группе пациенток ? у 14 из 20 женщин (70%. Использование ВМС ?Мирена? практически не повлияло на показатели липидного спектра. Нарушения менструального цикла по типу полименореи с однократным эпизодом меноррагии были выявлены лишь у 1 женщины. У остальных 95,4% женщин, имевших дисфункцию яичников по типу олиго- и опсоменореи, наблюдалась нормализация менструального цикла в среднем через 31 ?3,2 дней с длительностью кровопотери 4,6?1,7 дней. Выводы. Внутриматочные контрацептивные средства (медьсодержащие и левоноргестрелсодержащие обладают нейтральным эффектом на углеводный и липидный обмен у женщин, больных СД 1 типа, в период перименопаузы. У пациенток с удовлетворительной компенсацией СД на фоне применения ВМК показатели липидного спектра крови не ухудшаются. При плохой компенсации основного заболевания ухудшение липидного спектра крови происходит в виде повышения уровня ОХС, ХС ЛПНП и снижения ХС ЛПВП, что связано в большей степени с декомпенсацией углеводного обмена, а не с влиянием самого ВМК.

  3. Sravnenie gemodinamicheskikh i biokhimicheskikh effektov karvedilola i atenolola i ikh vliyanie na prognoz u bol'nykh sakharnym diabetom 2 tipa, perenesshikh epizod nestabil'noy stenokardii

    Directory of Open Access Journals (Sweden)

    L A Ivanova

    2008-06-01

    Full Text Available Цель. Сопоставить гемодинамические, биохими- ческие и прогностические эффекты карведилола и атенолола у больных СД 2, перенесших эпизод НС. Материалы и методы. В исследование включено 70 больных СД 2, осложнившимся НС. Во всех случаях диагностировались прогрессирующая стенокардия напряжения или впервые возникшая тяжелая стенокардия III?IV функциональных классов, по явившаяся в предшествующий месяц. Кроме общепринятой терапии НС, пациентам случайным образом выбирали для лечения ?-адреноблокатор карведилол ? до 25?50 мг/сут (1-я группа, n=35 или атенолол ? до 50?100 мг/сут (2-я группа, n=35. Выолнялись общеклинический анализ крови, биохимическое исследование крови, запись стандратной ЭКГ в 12 отведениях, эхокардиографическое исследование, тест с 6-минутной ходьбой. Результаты. Через полгода лечения карведилолом отмечалось значительное увеличение средней величины фракции выброса ЛЖ на 16,3%. Уменьшение выраженности дилатации полости ЛЖ приводило к увеличению относительной толщины его стенки (на 3,5% и снижению индекса сферичности (на 5,9%. Максимальная скорость раннего наполнения ЛЖ снижалась на 8,4%. Заключение. Карведилол обеспечивал тенденцию к снижению частоты повторных госпитализаций по поводу НС, случаев развития ИМ и наступления смерти по сравнению с атенололом. Однако главным образом из-за в целом небольшого количества наступавших осложнений эти различия не достигали уровня статистической значимости.

  4. K izučeniju kul'tury s keramikoj pražskogo tipa na territorii Moravii: formirovanije i osobennosti

    Czech Academy of Sciences Publication Activity Database

    Jelínková, Dagmar

    -, č. 5 (2015), s. 117-150 ISSN 1608-9057 Institutional support: RVO:68081758 Keywords : Prague-type pottery culture * Moravia * dating * Cultural relations to the east and South-East * Influence of the Merovingian sphere Subject RIV: AC - Archeology, Anthropology, Ethnology

  5. Two-dimensional selector type 2X3; Selecteur bidimensionnel type 2X3; Dvukhmernyj selektor tipa 2X3; Selector bidimensional tipo 2X3

    Energy Technology Data Exchange (ETDEWEB)

    Amram, Y [Centre d' Etudes Nucleaires de Saclay (France)

    1962-04-15

    This selector is intended for study of (n, {gamma}) reactions and has 2{sup 16} channels (1024 time channels and 64 amplitude channels). The characteristics (arrival time and amplitude) of each significant event are recorded, after coding, on a sixteen-track magnetic tape. The examination of the information on the tape is carried out in sections on a results analysis unit consisting of ae memory with 1024 channels which totals events having the same characteristics within an amplitude-time range set by the operator. The instrument has the following general characteristics: time selection, 1024 channels of width between 0.1 and 6.4 {mu}S divided into eight zones of interest of 128 channels; amplitude selection, 64 channels 0.25 to 1 V wide; average dead time, 7 {mu}s; resolution time of the complete apparatus is less than 20 {mu}s; conditioning for reading: it is possible to read a spectrum of times of flight in an amplitude band contained within any two limits. A similar operation can be carried out simultaneously for four amplitude spectra. (author) [French] Ce selecteur, destine a l'etude de reactions (n, {gamma}), comporte 2{sup 16} canaux (1024 canaux de temps x 64 canaux d'amplitude). Les caracteristiques (temps d'arrivee et amplitude) de chaque evenement interessant sont enregistrees, apres codage, sur une bande magnetique a seize pistes. Le depouillement du contenu de la bande magnetique s'effectue par parties sur un bloc d'exploitation de resultats comportant une memoire a 1024 canaux qui totalise les evenements presentant les memes caracteristiques a l'interieur d'un domaine amplitude-temps delimite par l'utilisateur. L'appareil possede les caracteristiques generales suivantes. Selection de temps, 1024 canaux de largeurs comprises entre 0,1 et 6,4 {mu}s groupes en huit zones d'interet de 128 canaux; selection d'amplitude, 64 canaux de 0,25 a 1 V de largeur; temps mort moyen, 7 {mu}s; temps de resolution de l'appareil complet, < 20 {mu}s; conditionnement a la lecture: possibilite de lire un spectre de temps de vol dans une bande d'amplitude comprise entre deux limites quelconques. Une operation analogue peut etre effectuee simultanement pour quatre spectres d'amplitudes. (author) [Spanish] Se trata de un selector distinado al estudio de reacciones n, {gamma}, que contiene 2{sup 16} canales (1024 canales de tiempo x 64 canales de amplitud). Las caracteristicas (tiempo de llegada y amplitud) de cada suceso interesante son codificadas y se registran en una cinta magnetica de dieciseis pistas. Los datos contenidos en la cinta se pasan por partes a un bloque de explotacion de los resultados que contiene una memoria de 1024 canales; dicho bloque totaliza los sucesos que presenten las mismas caracteristicas dentro de limites de amplitud y duracion establecidos por el experimentador. Las caracteristicas generales del aparato son las siguientes. Seleccion de tiempo, 1024 canales de anchos comprendidos entre 0,1 y 6,4 {mu}s, agrupados en ocho zonas de interes de 128 canales; seleccion de amplitud, 64 canales de 0,25 a 1 V de ancho; tiempo muerto medio, 7 {mu}s; tiempo de resolucion del conjunto del aparato, < 20 {mu}s; acondicionamiento en la lectura: posibilidad de leer un espectro de tiempos de vuelo en una banda de amplitud comprendida entre dos limites cualesquiera. Se puede realizar una operacion analoga simultaneamente para 4 espectros de amplitudes. (author) [Russian] EHtot selektor, prednaznachennyj dlya izucheniya reaktsij n, {gamma} sostoit iz 2{sup 16} kanalov (1024 kanalov vremeni i 64 amplitudnykh kanala). KHarakteristiki (vremya poyavleniya i amplituda) kazhdogo interesuyushchego sobytiya registriruyutsya posle kodirovaniya na magnitoj lente s 16 dorozhkami. Obrabotka soderzhaniya magnitnoj lenty osushchestvlyaetsya po chastyam na bloke pol'zovaniya rezul'tatami, soderzhashchimi zapominayushchee ustrojstvo s 1024 kanalami, kotoroe obobshchaet sobytiya, imeyushchie odinakovye kharakteristiki v sfere amplituda-vremya, ustanovlennye operatorom. Pribor obladaet sleduyushchimi obshchimi osobennostyami. Selektsiej vremeni, 1024 kanala shirinoj ot 0,1 do 6,4 {mu}s, sgruppirovannykh v 8 poleznykh zonakh po 128 kanalov v kazhdoj; amplitudnaya selektsiya, 64 kanala shirinoj ot 0,25 do 1 V; srednee mertvoe vremya, 7 {mu}s; polnoe razreshayushchee vremya ustanovki, 20 {mu}s; konditsionirovanie pri otschete: vozmozhnost' chitat' spektr vremeni proleta v amplitudnom diapazone mezhdu dvumya kakimi-nibud' predelami. Podobnaya operatsiya mozhet byt' osushchestvlena odnovremenno na 4 amplitudnykh spektrakh. (author)

  6. Opyt primeneniya ingibitora angiotenzinprevrashchayushchego fermenta spiraprila u bol'nykh gipertonicheskoy bolezn'yu v sochetanii s sakharnym diabetom 2 tipa

    Directory of Open Access Journals (Sweden)

    A F Tushova

    2008-06-01

    Full Text Available Цель. Оценка влияния иАПФ спираприла на плазменно-тромбоцитарный гемостаз, углеводный обмен и липидный профиль у больных ГБ, ассоциированной с СД 2. Материалы и методы. Под динамическим наблюдением находилось 33 больных СД 2 и ГБ (1-я ст. ? 2 (6,06%, 2-я ст. ? 9 (27,27%, 3-я ст. ? 22 (66,67% больных. Контрольную группу составили 35 больных гипертонической болезнью (1-я ст. ? 4 (11,43 %, 2-я ст. ? 14 (40 %, 3-я ст. ? 17 (48,57% без СД. Антропометрическое исследование включало измерение массы тела, объема талии (ОТ и бедер (ОБ, расчет ОТ/ОБ, индекса массы тела (ИМТ. Содержание глюкозы в крови определялось глюкозооксидазным методом в капиллярной крови натощак, через 1 и 2 часа в ходе стандартного перорального глюкозотолерантного теста с 75 г глюкозы. Исследовались липидный спект, экскреция альбумина, коагуляцинное звено гемостаза, тромбоцитарное звено гемостаза. Результаты. МАУ (экскреция альбумина >20 мг/л исходно диагностирована у 28 больных (84,85%. Через 4 недели лечения спираприлом у 93,94% больных отмечалось уменьшение уровня экскреции альбумина с мочой. У обследованных больных СД 2 с ГБ отмечены нарушения во всех звеньях гемостаза, но, в отличие от контрольной группы, были менее выражены нарушения спонтанной агрегации тромбоцитов. У больных СД с ГБ гиперкоагуляция наблюдалась преимущественно по внешнему пути свертывания крови. Заключение. У больных СД и ГБ повышен тромбогенный потенциал крови. В результате лечения спираприлом отмечена положительная динамика ? активация фибринолитической системы, снижение спонтанной агрегации тромбоцитов и нормализация в коагуляционном звене гемостаза. На фоне терапии спираприлом наблюдается улучшение показателей углеводного и липидного обмена. Спираприл обладает нефропротективным эффектом, что проявилось снижением уровня МАУ. Лечение спираприлом не влияло на динамику массы тела, ИМТ, отношения ОТ/ОБ.

  7. In core-fuel management in approach to equilibrium of WWER-440 reactor; Prelazni rezim iskoriscenja goriva u nuklearnom reaktoru tipa VVER-440

    Energy Technology Data Exchange (ETDEWEB)

    Marinkovic, N [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1978-07-01

    For the need of in core fuel management and prediction of fuel cycle costs as well as operating of a nuclear power plant behaviour of main physical parameters and refueling scheme during approach to equilibrium operation are indispensable. An estimation of a refueling scheme during forst six years of exploitation for a commercially proven PWR reactor of WWER-440 type is shown in this paper. (author)

  8. Safety characteristics analysis of nuclear power plants with PHWR PT; Analiza sigurnosnh karakteristika nuklearnih elektrana sa reaktorima PHWR-PT tipa

    Energy Technology Data Exchange (ETDEWEB)

    Stosic, Z [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1983-07-01

    The paper deals with analysis of basic safety characteristics of heavy water Candu reactor. Inherent safety characteristics, r/a material inventory, systematization of normal abnormal and transient conditions, safety systems and availability analysis are considered. (author)

  9. Safety analysis of RA reactor operation, I-III, Part III - Environmental effect of the maximum credible accident; Analiza sigurnosti rada reaktora RA - I-III, III deo - Posledica maksimalno moguceg akcidenta na okolinu reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    Maximum credible accident at the RA reactor would consider release of fission products into the environment. This would result from fuel elements failure or meltdown due to loss of coolant. The analysis presented in this report assumes that the reactor was operating at nominal power at the moment of maximum possible accident. The report includes calculations of fission products activity at the moment of accident, total activity release during the accident, concentration of radioactive material in the air in the reactor neighbourhood, and the analysis of accident environmental effects.

  10. RA Reactor operation and maintenance (I-IX), part VII, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora (I-IX), VII Deo, Zadatak 3.08/04 Remont reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This volume covers the following reports concerned with the maintenance and repair work of the RA reactor: repair of the technical water system; maintenance of the transportation equipment; vacuuming and drying during refurbishment; repair and decontamination of the distillation device; and the report on participation of the operational dosimetry division in the RA reactor refurbishment activities.

  11. RA Research reactor, Part I: Technical and operational properties of the RA reactor; Analiza sigurnosti rada Reaktora RA I-III, Deo I: Tehnicke i pogonske karakteristike reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Zecevic, V; Nikolic, M; Popovic, B; Milosevic, M; Milic, M; Strugar, P; Pesic, M; Nikolic, V; Rajic, M; Radivojevic, J; Jankovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    RA reactor is a research reactor with rather high power density. Apart from research it is used for isotope production and industrial applications due to high reactivity excess (about 11%). It is a thermal reactor, heavy water moderated, cooled by D{sub 2}O, and H{sub 2}O, with a graphite reflector. Nominal power is 6.5 MW. Fuel is 2% enriched metal uranium, reactor core height is 1220 mm, and diameter is 1405 mm. Reactor lattice is square with lattice pitch 130 mm. There is 6 horizontal experimental channels and a graphite column. There is a total of 84 fuel channels and 45 experimental channels in the core. Maximum thermal neutron flux is 5.5 10{sup 13} n/cm{sup 2} s at nominal power level.

  12. Theoretical analysis of nuclear reactors (Phase III), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-IV, III Deo, Zatrovanje reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    Report on calculation of poisoning in experimental and power reactor includes four parts. Part one describes the influence of poisoning on the physical parameters of a reactor. part two includes transformation of differential equations for iodine and xenon. It was needed for easier solution of of differential equation using the analog computer. This calculation was done for RA reactor operating at 5 MW power. The RA reactor was used an example of calculation by the proposed method. Part four shows the application of the method for calculating the Calder Hall power reactor.

  13. RA reactor safety analysis I-III, Part III - Environmental effect of the maximum credible accident; Analiza sigurnosti rada Reaktora RA I-III, III deo - Posledica maksimalno moguceg akcidenta na okolinu reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    The objective of the maximum credible accident analysis was to determine the integral radiation doses in the vicinity of the reactor and in the environment. In case of RA reactor the maximum credible accident, meaning release of the fission products, would be caused by fuel elements meltdown. This analysis includes the following calculation results: activity of the fission products, volatility of the fission products, concentration of radioactive materials in the air, analysis of the accident environmental effects.

  14. Safety analysis of RA reactor operation, I-II, Part I - RA reactor technical and operation characteristics; Analiza sigurnosti rada reaktora RA - I-III, I deo - Tehnicke i pogonske karakteristike reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    RA research reactor is a thermal, heavy water moderated system with graphite reflector having nominal power 6.5 MW. The 2% enriched metal uranium fuel in the reactor core produces mean thermal neutron flux of 2.9 10{sup 13} neutrons/cm{sup 2} s, and maximum neutron flux 5.5 10{sup 13} neutrons/cm{sup 2} s. main components of the reactor described in this report are: rector core, reflector, biological shield, heavy water cooling system, ordinary water cooling system, helium system, reactor control system, reactor safety system, dosimetry system, power supply system, and fuel transport system. Detailed reactor properties and engineering drawings of all the system are part of this volume.

  15. RA Reactor operation and maintenance (I-IX), part VIII, Task 3.08/05, Decontamination of the reactor; Pogon i odrzavanje reaktora (I-IX), VIII Deo, Zadatak 3.08/05 Dekontaminacija reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Permanent increase of radiation in the heavy water system was noticed during first three year of the RA reactor operation, even when the reactor was shutdown. It was found that there was no failure of the fuel element cladding. Radioactive cobalt was found in the heavy water which was rather strange. During repair of the heavy water system, it has been found that stellite was used for coating the heavy water pumps. Since stellite is a cobalt alloy, this could have been the source of radioactive cobalt in the heavy water. The stellite coating was damaged due to friction and particle of cobalt appeared in the coolant, they were activated since they were in the core. decontamination of the heavy water and the heavy water coolant loop was a must . Beside the detailed report on the contamination and decontamination of the heavy water system this volume includes 14 annexes describing the investigation of the event and the whole procedure of decontamination.

  16. RA Reactor operation and maintenance (I-IX), Part IV, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora RA (I-IX), IV Deo, Zadatak 3.08/04 Remont reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This volume contains reports describing maintenance and repair work of the RA reactor instrumentation, equipment of the reactor dosimetry control system, and equipment for regulation and control systems.

  17. Theoretical analysis of nuclear reactors (Phase I), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, III Deo, Zatrovanje reaktora, I faza

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    Method was developed for calculation of Xe{sup 135} static effect and kinetic effects of Xe{sup 135} and Sm{sup 149} with separate treatment of iodine effect and influence of reactor poisoning during power increase. Mentioned effects are treated first for uranium fuel and then the basic formulae were generalized for a mixture of fissile material. The annex contains a table with data needed for calculations and the Xe{sup 135} microscopic capture cross section dependent on temperature. Razradjen je metod proracuna statickog efekta Xe{sup 135} zatim kinetickog efekta Xe{sup 135} i Sm{sup 149} sa posebnim tretiranjem jodne jame i promene zatrovanja pri prelazu sa jedne snage na drugu. Navedeni efekti su tretirani prvo za uransko gorivo, a zatim su glavni obrasci uopsteni za smesu fisibilnih materijala. U prilogu su dati u vidu tabele, podaci potrebni za proracun i grafik zavisnosti mikroskopskog preseka zahvata Xe{sup 135} od temperature.

  18. Theoretical analysis of nuclear reactors (Phase II), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, III Deo, Zatrovanje reaktora, II faza

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    This phase is dealing with influence of all the fission products except Xe{sup 135} on the reactivity of a reactor, usually named as reactor poisoning. The first part of the report is a review of methods for calculation of reactor poisoning. The second part shows the most frequently used method for calculation of cross sections and yields of pseudo products (for thermal neutrons). The system of equations was adopted dependent on the conditions of the available computer system. It is described in part three. Detailed method for their application is described in part four and results obtained are presented in part five.

  19. RA Reactor operation and maintenance (I-IX), part VI, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora (I-IX), VI Deo, Zadatak 3.08/04 Remont reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    During the period planned for maintenance and refurbishment of the RA reactor the gas reactor system including the ventilation system was inspected and tested, the components were cleaned. This report describes detailed instructions and actions concerning repair and decontamination of the gas and ventilation systems components.

  20. Study of power reactor dynamics by stochastic reactor oscillator method; Proucavanje dinamike reaktora snage metodom stohastickog reaktorskog oscilatora

    Energy Technology Data Exchange (ETDEWEB)

    Velickovic, Lj; Petrovic, M [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1968-12-15

    Stochastic reactor oscillator and cross correlation method were used for determining reactor dynamics characteristics. Experimental equipment, fast reactor oscillator (BOR-1) was activated by random pulses from the GBS-16 generator. Tape recorder AMPEX-SF-300 and data acquisition tool registered reactor response to perturbations having different frequencies. Reactor response and activation signals were cross correlated by digital computer for different positions of stochastic oscillator and ionization chamber.

  1. Study of heterogeneous nuclear reactor lattice properties in multizone systems; Ispitivanje karakteristika resetke heterogenih nuklearnih reaktora u visezonim sistemima

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Described analysis of substitution experiments and its comparison with the classic procedures showed that it could be successfully applied for processing the experimental results. This method shows some advantages and some deficiencies compared to classic methods. Precision of the method is considered sufficient for design of nuclear facilities. Routine standards used in design of nuclear facilities demand following precision of nuclear parameters: about 5% during feasibility study and design of heavy water facility with natural uranium; 2 - 3% in the phase of parameters optimisation and preparing the main project; 1% during optimization of operation. Accuracy of core parameters obtained by analysis of substitution experiments show that they could be successfully used in the phase of reactor parameters optimisation. It is possible to increase the precision of critical parameters and thus apply the proposed method for analysis of reactor parameters needed in the phase of operation optimization.

  2. Operation and maintenance of the RA reactor in 1965; Pogon i odrzavanje reaktora RA. Izvestaj o radu u 1965. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-01-15

    It has been planned for 1965 that the RA reactor would be operated each month for 20 days at nominal power of 6.5 MW, at lower power for 5 days, meaning production of 27 400 MWh. The plan was fulfilled since reactor produced 28809 MWh, i.e. 5% more than planned. Reactor was used for irradiation in the vertical experimental channels according to the demand of 1264 users from the Institute and 191 external users. Two groups of experiments done: at nominal power simultaneously with isotope production and experiments which demanded particular power levels and temperatures. Three fuel exchanges were done during this year, meaning that 40 fuel channels were changed in total. Vertical experimental channels VEK-1 and VEK-9 having diameter 100 mm were changed by channels having diameter 50 mm and shortened by 435 mm. Channel VEK-5 with diameter 110 mm was changed shortened by 430 mm. This enabled better fuel economy, the burnup was increased from 4500 MWd/t to 5000 MWd/t. This report contains the action plan for 1966.

  3. RA Reactor operation and maintenance (I-IX), Part I; Pogon i odrzavanje reaktora RA (I-IX), I Deo

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    The report on RA reactor operation and maintenance for year 1963 is divided in six tasks. This volume contains the introductory report, and three tasks of the final report, namely reactor exploitation, reactivity changes of the RA reactor before repair, planning of refuelling.

  4. Accident analysis of RB reactor dependent on the lattice pitch; Akcidentalna analiza reaktora ''RB'' pri promeni koraka resetke

    Energy Technology Data Exchange (ETDEWEB)

    Lolic, B; Lazarevic, B [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1963-07-01

    This analysis was concerned with reactor core with 52-56 fuel rods, lattice pitch being, 8, 10, 12, 16, 18, and 20 cm. Measured values of excess reactivity above critical level of 3.85 cm, total anti reactivity of regulating rod, reactivity changes caused by pumping heavy water and reactivity variations due to movement of control rod were used. Three types of accidents were analyzed: movement of regulating rod to the position of zero reactivity worths, increase of heavy water level at rate of 2.5 cm/min, combination of two previous accidents.

  5. Epithermal neutron flux in the experimental channels of the RA reactor; Fluks epitermalnih neutrona u eksperimentalnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Dobrosavljevic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Epithermal neutron flux was determined by measuring the cadmium ratio from activation analysis of gold and indium foils. Irradiation was done in experimental channels VK-5, VK-2, VK-7, VK-0, VK-HS next to the core, and next to the fuels elements. Activation of bare foils and foils covered by 0.8 and 1.0 mm thick cadmium foils was done simultaneously. Activity was measured by GM counter. Corrections were done for resonant neutrons self-absorption since the foils used were too thick concerning most important resonances of gold and indium. Final results were presented as spectrum factor r for their direct use in determining the effective neutron cross sections.

  6. Neutron measurements inside reactors with semiconductor counters; Apsolutno merenje neutronskih flukseva u jezgru reaktora RA visokim snagama

    Energy Technology Data Exchange (ETDEWEB)

    Ajdacic, V; Lalovic, B; Barucija, M; Petrovic, B [Institute of Nuclear Sciences Boris Kidric, Laboratorija za fiziku i dinamiku reaktora, Vinca, Beograd (Serbia and Montenegro)

    1964-06-15

    A method of absolute in-core measurement of high neutron fluxes inside reactors operating in the megawatt region is described. In this method a semiconductor counter observes particles coming from neutron induced reactions in a target placed inside the reactor core through a long evacuated aluminum tube. The paper deals with factors which influence the accuracy of the method. Possible use of the long- tube method for neutron flux measurements in advanced reactors with neutron flux of 10{sup 15}-10{sup 16} n/cm{sup 2} sec is also discussed. The possibility of using the Li{sup 6} semiconductor counter spectrometer for measuring fast neutron spectra inside the zero power reactor at Vinca has been investigated. Great difficulties associated with the high interference of thermal neutrons have been encountered. The thermal neutron interference is almost completely suppressed by a new detector-target arrangement, in which only those products of the Li{sup 6} (n,alpha)T reactions whose mutual angle of emission is different from 180 deg are detected in coincidence. Resolution of the spectrometer as a function of the reactor power and correction factors of the spectrometer efficiency for various neutron energies are presented (author)

  7. Operation of the RA research nuclear reactor under forced regime; Rad istrazivackog nuklearnog reaktora RA u forsiranom rezimu

    Energy Technology Data Exchange (ETDEWEB)

    Mitrovic, S [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Ra reactor was designed for operation at nominal power of 6.5 MW and under forced regime. From the start of operation in 1959 until the general refurbishment in 1963 it was not operated under forced regime. At reactor power of 10 MW the mean thermal neutron flux increases from 3 to 4.6 10{sup 13} n cm{sup -2} sec{sup -1}, the maximum neutron flux increases from 6 to 9.3 10{sup 13} n cm{sup -2} sec{sup -1}, and at the exit of the experimental channel it increases from 5 to 7.7 10{sup 9} n cm{sup -2} sec{sup -1}. In order to achieve safer and more suitable operating conditions, winter period of 1963 was chosen for the first increase of reactor power level, because of low temperatures in the secondary coolant loop. This paper contains the most relevant data concerned with the reactor operation at increased power.

  8. Nuclear Reactor RA Safety Report, Vol. 9, Radiation protection; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 9, Zastita od zracenja

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Instrumentation for Radiation protection existing at the RA reactor is dating mostly from the period 1957-1959 when the reactor has been built. With some minor exception it was produced in USSR. Radiation protection system was constructed based on specific design project, somewhat modified original USSR project which has been indispensable because of some modification of the building design. During the past 27 years no renewal of the instrumentation was done, only maintenance was performed. Instrumentation consists of old electronic devices which caused difficulties and even prevented regular maintenance because of lack of spare parts. Instrumentation for radiation protection at the RA reactor is classified as follows: centralized dosimetry system; stationary dosimetry instrumentation, movable and personal dosimetry systems. Apart from the scheme of dosimetry instrumentation this volume includes description of radiation protection procedures; protection devices; radiation doses and dose limit data; program for environmental radioactivity control; medical control procedures. [Serbo-Croat] Instrumentacija za zastitu od zracenja koja danas postoji na reaktoru RA najvecim delom potice iz perioda 1957-1959 kada je reaktor gradjen. Sa malim izuzetcima instrumentacija je proizvedena u SSSR. Sistem za zastitu izveden je na osnovu posebnog projekta koji predstavlja modifikaciju originalnog projekta koja je bila neophodna usled modifikovanog gradjevinskog projekta. U proteklom periodu od 27 godina instrumentacija nije obnavljana vec je vrseno samo odrzavanje. Instrumentacija je izradjena u danas prevazidjenoh tehnoligiji (elektronske cevi) sto je otezavalo i skoro onemogucavalo normalno odrzavanje. Instrumentacija za zastitu od zracenja na reaktoru RA moze se podeliti na tri dela: centralizovani dozimetrijski sistem; stacionarna dozimetrijska instrumentacija; prenosna i licna dozimetrijska instrumentacija. Pored seme sistema dozimetrijske kontrole ova knjiga sadrzi opis postupaka zastite od zracenja; zastitne opreme; podatke o dozama zracenja i granicne vrednosti; program kontrole radioaktivnosti okoline; mere medicinske kontrole.

  9. Response to local reactivity perturbation of thermal multizone reactors; Odziv termalnih multizonih reaktora na lokalnu perturbaciju reaktivnosti

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D; Jevtovic, V [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

    1966-07-01

    This paper describes application of the mode analysis, spatial eigenfunction expansion for solving the time dependent diffusion equation in two-group approximation, for the case of time dependent absorption cross section in the thermal region. Transfer functions for radially multi zone and homogeneous reactor systems were obtained as results of solving the time-dependent diffusion equation. Some numerical results obtained by applying this method are given as well. U radu je primenjena modalna analiza, razvoj po prostornim svojstvenim funkcijama, za resavanje vremenski zavisne difuzione jednacine u dvogrupnoj aproksimaciji, kada je presek za apsorpciju u termalnoj grupi funkcija vremena. Kao rezultat resavanja vremenski zavisne difuzione jednacine dobijeni su izrazi za prenosne funkcije radijalno multizonih reaktorskih sistema i homogenih reaktorskih sistema. Dati su i neki numericki rezultati primene ove metode (author)

  10. Response of thermal multi zone reactors to local perturbation of reactivity; Odziv termalnih multizonih reaktora na lokalnu perturbaciju reaktivnosti

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D; Jevtovic, V [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1967-01-15

    A modal analysis method, spatial eigenfunctions expansion, was applied for solving the time dependent diffusion equation in two-group approximation. The absorption cross section in the thermal neutron range was time dependent. The response functions for radially multi-zone reactor systems and homogeneous reactors were obtained as solutions of the time dependent diffusion equation. Some numerical results obtained by this method are included. U radu je primenjena modalna analiza, razvoj po prostornim svojstvenim funkcijama, za resavanje vremenski zavisne difuzione jednacine u dvogrupnoj aproksimaciji, kada je presek za apsorpciju u termalnoj grupi funkcija vremena. Kao rezultat resavanja vremenski zavisne difuzione jednacine dobijeni su izrazi za prenosne funkcije radijalno multizonih reaktorskih sistema i homogenih reaktorskih sistema. Dati su i neki numericki rezultati primene ove metode (author)

  11. Annex 2 - Design concept of RA reactor fuel element fabrication; Prilog 2 - Koncepcija izrade gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, M; Mihajlovic, A; Ristic, M; Simic, G [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This document shows the construction and description of the individual parts of the fuel element. Planned procedures for fabrication of Al cladding and the fuel element structure are presented. Within the analysis of the results, claddings obtained by applying the proposed procedure are presented as well as the future plans. Dat je prikaz konstrukcije sa opisom i ulogom pojedinih sastavnih delova i sklopa gorivnog elementa. Izneta su predvidjanja za izradu, kako Al kosuljice, tako i sklopa gorivnog elementa. U analizi dosadasnjih rezultata, prikazane su kosuljice dobijene po navedenim postupcima, kao i smernice daljeg rada (author)

  12. RA reactor safety analysis, Part II - Accident analysis; Analiza sigurnosti rada Reaktora RA I-III, Deo II - Analiza akcidenta

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Radanovic, Lj; Milovanovic, M; Afgan, N; Kulundzic, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This part of the RA reactor safety analysis includes analysis of possible accidents caused by failures of the reactor devices and errors during reactor operation. Two types of accidents are analyzed: accidents resulting from uncontrolled reactivity increase, and accidents caused by interruption of cooling.

  13. Fast neutron flux in the RA reactor experimental channels; Fluks brzih neutrona u eksperimentalnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Dobrosavljevic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Fast neutron flux in the RA reactor experimental channels was determined by using threshold reaction detectors. The (n,p) type reactions S{sub 32} (n,p)P{sub 32}, and Al{sub 24} (n,p)Na{sub 24}. Prepared sulphur and phosphorous foils were placed in cadmium boxes and irradiated in experimental channels VK-5, VK-7 and VK-9. Gold foils were irradiated simultaneously for controlling the reactor power. Reactor power was 100 kW during irradiation of half an hour. Activity of P{sub 32} and S{sub 31} after reactor shutdown was measured by 4{pi} counter and three calibrated GM counters. Absolute neutron flux was determined by using thus obtained data.

  14. Investigation of the heavy water distillation system at the RA reactor; Ispitivanje sistema za destilaciju teske vode reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Badrljica, R [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    The heavy water distillation system was tested because this was not done before the reactor start-up. Detailed inspection of the system components showed satisfactory results. Leak testing was done as well as the testing of the instrumentation which enables reliable performance of the system. Performance testing was done with ordinary water and later 2700 l of heavy water from the reactor was purified, decreasing the activity by 45%.

  15. Program of RA reactor start-up to nominal power; Program dizanja reaktora 'RA' na nominalnu snagu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-01

    The zero start-up program is followed by the program of RA reactor start-up to nominal power. This program is desed in detail and includes the following measurements: radiation characteristics at the exit of the channels; gamma and fast neutron dose distribution in the reactor; influence of absorbers on the reactivity; temperature effect; absolute flux and calibration of ionization chambers; xenon effect; thermal and hydraulics; dosimetry around the reactor; neutron flux in the reactor core and in the reactor hall; heavy water level; thermal characteristics after shutdown. A list of measuring devices and instrumentation is included with the detailed action plan and list of responsible staff members.

  16. Choice of the type of a storage for the centre of processing and burial of RAW in Ukraine.; Vybor tipa khranilishch dlya Tsentra pererabotki i zakhoroneniya radioaktivnykh otkhodov v Ukraine.

    Energy Technology Data Exchange (ETDEWEB)

    Korchagin, P A; Avdeev, O K; Bogachev, O M [Naukovo-Tekhnyichnij Tsentr z dezaktivatsyiyi ta kompleksnogo povodzhennya z radyioaktivnimi vyidkhodami, Zhovtyi Vodi (Ukraine)

    1994-12-31

    Variants of arrangement of the Centre of processing and burial of low-and middle-active RAW and a design of storages have been considered. Types of burials and kinds of tanks have been determined with regard for the properties providing for both safety and economical storage of RAW and depending on radionuclide composition of waste placed to them.

  17. Peculiarities of phenotype and genetic statuses of diabetes mellitus patients living on contaminated areas; Osobennosti fenotipicheskogo i geneticheskogo statusa lits s sakharnym diabetom 1 tipa, prozhivayushchikh na zagryaznennoj territorii

    Energy Technology Data Exchange (ETDEWEB)

    Mel' nov, S B; Morozik, V M; Mokhort, T V [International A. Sakharov environmental univ., Minsk (Belarus)

    2006-05-15

    Some peculiarities of cytogenetic status of the Diabetes Mellitus patients from areas with different level of ecology pressure were investigated. We found pronounced increase practically all types of aberrations. Comparative anthropology investigations showed real differences in status of children from mail group (citizens of radiation contaminated areas). (authors)

  18. Nitrided steel 38CrN3MAFA for supporting elements in nuclear power plants; Vysokoazotistaya stal` tipa 38HN3MAFA dlya krepezhnikh detajlej reaktorov AEhS

    Energy Technology Data Exchange (ETDEWEB)

    Rasheva, I; Argirov, Kh; Stojchev, T [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. po Metaloznanie i Tekhnologiya na Metalite

    1996-12-31

    Nitride doping of steel at different concentrations is achieved by counter-pressure casting in nitrogen ambience. A new type of steel is developed containing 0.05-0.2% N{sub 2}. It is compared to a standard 34NiCrMoV145 steel (DIN). The mechanical properties are improved significantly after a two-stage thermal treatment and are as follows: fluidity limit R{sub 0}.2>=1045 MPa, relative elongation A>=15%, relative shortening Z>=62%, impact viscosity KCU >= 1 MJ/m{sup 2}. The quench hardening consists of heating to 800-850{sup o} C in oil and cooling to 600{sup o} C in air. The steel is suitable for rotors, turbines, compressor shafts and reactor supporting elements in nuclear power plants. 3 refs., 6 figs., 6 tabs.

  19. Electrical characteristics of sphere-plane type spark counters; Caracteristiques electriques de compteurs a etincelles du type sphere-plan; Ehlektricheskie kharakteristiki iskrovykh schetchikov tipa shar-ploskost'; Caracteristicas electricas de los contadores de chispas del tipo esfera-plano

    Energy Technology Data Exchange (ETDEWEB)

    Laborie, P; Blanc, D [Centre de Physique Nucleaire, Faculte des Sciences de Toulouse (France)

    1962-04-15

    The authors describe here the mechanical construction and operating characteristics of spark detectors using a small (0.30 mm) diameter sphere as anode, set opposite to a plane cathode and working by the ''corona'' effect, in air at atmospheric pressure. Counting characteristics are very similar to those of Rosenblum-type anode wire detectors. However, the sphere counter has a certain superiority over the Rosenblum counter inherent in its geometry : (a) there sidual current (background) is low and the release of ozone and nitrous oxides during the spark is not of great significance; (b) its self-capacity being very small, the detector gives a faster response; (c) unlike in the case of wire counters, efficiency is independent of particle incidence direction; (d) its sensitive volume, that of a solid of revolution around the axis of symmetry of the detector, amounts to a few cubic millimetres and, being very clearly defined, permits realization of accurate telescopic devices. (author) [French] Les auteurs decrivent la realisation mecanique et les caracteristiques de fonctionnement de detecteurs a etincelles utilisant comme anode une sphere de petit diametre (0,30 mm), disposee en regard d'une cathode plane, et fonctionnant en regime d'effet , dans l'air sous la pression atmospherique. Les caracteristiques de comptage sont voisines de celles des detecteurs a fil anodique, du type Rosenblum. Le compteur a sphere presente cependant sur le compteur de Rosenblum un certain nombre d'avantages lies a sa geometrie: a) le courant residuel (bruit de fond) est faible, et le degagement d'ozone et d'oxydes de l'azote lors des etincelles est peu considerable; b) sa capacite propre etant tres petite, le detecteur presente une reponse plus rapide; c) l'efficacite est independante de la direction d'incidence de la particule, contrairement a ce qui a lieu pour les compteurs a fil; d) le volume sensible de revolution autour de l'axe de symetrie du detecteur, qui est de quelques millimetres cubes, est tres bien defini, ce qui permet la construction de telescopes precis. (author) [Spanish] Los autores describen los detalles mecanicos y las caracteristicas de funcionamiento de unos detectores de chispas en que se utiliza como anodo una esfera de pequeno diametro (0,30 mm), dispuesta frente a un catodo plano y que funcionan en regimen de efecto , en aire a presion atmosferica. Las caracteristicas de contaje son semejantes a las de los detectores de anodo de alambre, de tipo Rosenblum. No obstante, el contador de esfera presenta, con respecto a dicho contador Rosenblum, cierto numero de ventajas derivadas de su geometria: a) la corriente residual (ruido de fondo) es debil y el desprendimiento de ozono y de oxidos de nitrogeno, con las chispas, es poco considerable; b) como su capacidad propia es muy pequena, el detector ofrece una respuesta mas rapida; c) la eficiencia es independiente de la direccion de incidencia de la particula, al reves de lo que ocurre con los contadores de alambre; d) el volumen sensible de revolucion en torno del eje de simetria del detector es de algunos milimetros cubicos y esta muy bien definido, lo que permite la construccion de telescopios de gran precision. (author) [Russian] Avtory opisyvayut mekhanicheskuyu konstruktsiyu i rabochie kharakteristiki iskrovykh schetchikov, v kotorykh v kachestve anoda ispol'zuetsya shar malogo diametra (0,30 mm), raspolozhennyj protiv ploskogo katoda. Ehti schetchiki rabotayut v rezhime ''kol'tsevogo'' yavleniya (''korony'') v vozdukhe pri atmosfernom davlenii. Schetnye kharakteristiki blizki k kharakteristikam schetchikov Rozenblyuma s anodnym provodom. Sharovoj schetchik imeet, odnako, nekotorye preimushchestva po sravneniyu so schetchikom Rozenblyuma, chto svyazano s ego geometriej: 1. ostatochnyj tok (fon) slabyj, a vydelenie ozona i okisi azota vo vremya iskreniya neznachitel'no. 2. Poskol'ku ego sobstvennaya emkost' ochen' mala, schetchik daet bolee bystryj otvet. 3. Ehffektivnost' ne zavisit ot napravleniya padeniya chastitsy v protivopolozhnost' tomu, chto kharakterno dlya provodnykh schetchikov. 4. Chuvstvitel'nyj ob'em vrashcheniya vokrug osi simmetrii schetchika ravnyaetsya neskol'kim kubicheskim millimetram; on ochen' tochno opredelen, chto pozvolyaet sooruzhat' tochnye teleskopy. (author)

  20. Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca; Radovi za potrebe eksploatacije reaktora RA - I-IV, II Deo, Predprojekat VI-SA 1, Petlja za ispitivanje gorivnih elemenata reaktora EL-4 u centralnom vertikalnom eksperimentalnom kanalu reaktora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO{sub 2} with beryllium cladding, cooled by CO{sub 2} under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO{sub 2}. This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment.

  1. Spatial distribution of reactor radiation around the horizontal experimental hole of the RA Reactor at Vinca; Prostorna raspodela reaktorskog zracenja oko horizontalnog eksperimentalnog kanala reaktora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Paligoric, D; Vujisic, B [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1964-10-15

    A survey is given of the measurement of the spatial distribution of thermal and fast neutrons and gamma radiations inside and around the reactor radiation beam which is carried through the experimental channel outside the reactor biological shield thus being a potential danger for the personnel in the reactor hall. The results obtained are used to determine the optimal distribution of the shielding elements around the free radiation beam. The activation method was used to determine the distribution of slow and fast neutrons. The detectors were Au{sup 197} and In {sup 115} for slow, and the S{sup 32} (n,p) P{sup 32} reaction for fast neutrons. The relative distribution of slow and fast neutrons along the beam axis in the space outside the reactor, and evaluation of the absolute value of the flux at the place where the beam comes out from the biological shield are given (author)

  2. Testing measurements at horizontal channels of the MARIA reactor performed using neutron spectrometers; Pomiary testowe przy kanalach poziomych reaktora MARIA wykonane przy uzyciu spektrometrow neutronow

    Energy Technology Data Exchange (ETDEWEB)

    Murasik, A. [Institute of Atomic Energy, Otwock-Swierk (Poland)

    1997-12-31

    By means of neutron diffraction, using the standard polycrystalline sample of Al{sub 2}O{sub 3}, measurements on three (of four spectrometers) already installed in the front of horizontal channels of MARIA reactor have been performed. Basing on these experiments as well as on activation measurements carried out earlier, the fluxes of monoenergetic neutrons have been estimated. These experiments allowed to determine (for a given geometry and kind of monochromators chosen) the resolution efficiency of instruments and high order contamination in the reflected beam. With the help of polycrystalline vanadium and TbBr{sub 3} sample, the possibility of studies using the inelastic scattering process have been tested. (author) 7 refs, 15 figs, 7 tabs

  3. Dosimetry and radiation protection at the RA reactor, Report for 1978 - Annex V; Prilog V - Dozimetrija i tehnicka zastita od zracenja kod reaktora RA - Izvestaj za 1978. godinu -

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M et al [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    This annex includes data about measured levels of gamma and neutron irradiation as well as level of contamination of the working environment. In addition it covers data about irradiation of the staff, contamination, decontamination of the surfaces, and radioactive waste. During 1978 there were no significant accidents that could impact either staff or the environment. [Serbo-Croat] Ovaj prilog sadrzi podatke o merenim nivoima gama i neutronskog zracenja kao i stepenu kontaminacije radne sredine na reaktoru RA. Pored toga dati su podaci o ozracivanju osoblja, kontaminaciji, dekontaminaciji i radioaktivnom otpadu. Akcidenata vecih razmera koji bi imali znacajnije posledice po osoblje i okolinu tokom 1978. godine nije bilo.

  4. Measurement of rod-drop time for control and safety rods at the RB reactor; Merenje vremena pada kontrolne sipke i sigurnosnih sipki reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M; Marinkovic, P; Stefanovic, D [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1990-12-15

    The objective of this task was to determine the thermal utilization factor f in a heterogeneous reactor cell. For this purpose reliable data about thermal neutron spatial distribution are needed. Spatial distribution of the thermal neutron flux in the reactor cell was measured by perturbation method which showed best results compared to other methods described in this paper experiments were done at the RB reactor.

  5. Estimation of the influence of nuclear reactors in Vinca on the radiation situation in Belgrade; Procena uticaja nuklearnih reaktora u Vinci na radijacionu situaciju u Beogradu

    Energy Technology Data Exchange (ETDEWEB)

    Marsicanin, B [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1981-07-01

    Both reactors RB and RA were built in the period of non existing environmental regulations nor IAEA recommendations. The objective of this study was to review the present radiation situation on the territory of Belgrade, especially the influence of these reactors which could arise in case of some emergency or possible accidental event. This report includes detailed technical data, demographic, meteorological and other information which are significant for the analysis of accidental radioactivity release from the reactors in Vinca.

  6. Dosimetry and radiation protection at the RA reactor, Report for 1976 - Annex V; Prilog V - Dozimetrija i tehnicka zastita od zracenja kod reaktora RA - Izvestaj za 1976. godinu -

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M et al [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    This annex includes data about measured levels of gamma and neutron irradiation as well as level of contamination of the working environment. In addition it covers data about irradiation of the staff, contamination, decontamination of the surfaces, and radioactive waste. During 1976 there were no significant accidents that could impact either staff or the environment. [Serbo-Croat] Ovaj prilog sadrzi podatke o merenim nivoima gama i neutronskog zracenja kao i stepenu kontaminacije radne sredine na reaktoru RA. Pored toga dati su podaci o ozracivanju osoblja, kontaminaciji, dekontaminaciji i radioaktivnom otpadu. Akcidenata vecih razmera koji bi imali znacajnije posledice po osoblje i okolinu tokom 1976. godine nije bilo.

  7. Measurement of the heavy water level in the fuel channels of the RA reactor - Annex 11; Prilog 11- Merenje nivoa teske vode u gorivnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    The objective of measuring the heavy water level in the reactor channels was to verify experimentally the possibilities of reactor cooling with parallel operation of heavy water pumps od 1500 rotations/min at nominal power of 6.5 MW. Measurements were done in 2 periphery and 2 central fuel channels with pumps speed 1500, 1800 and 3000 rotations/min by a contact probe with electric resistance measuring device. precision of the measurement was {+-}1 cm.

  8. Analysis of neutron flux increase in the horizontal experimental channels of Ra reactor - masters thesis; Analiza povecanja neutronskog fluksa na horizontalnim eksperimentalnim kanalima reaktora RA - magistarski rad

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1964-12-01

    Calculation and experimental results shown in this paper show that higher thermal neutron flux is obtained in the reactor core with central horizontal reflector at the same power level. The flux is increased when the moderation capability of the core is decreased. Apart from increase of the thermal component of the neutron flux in the experimental channels, the central reflector causes decrease of the epithermal neutron flux and gamma radiation intensity. This is very useful for studying (n, {gamma}) reaction, neutron diffraction, etc. [Serbo-Croat] Rezultati proracuna i merenja prikazanih u ovom radu ukazuju na cinjenicu da se u reaktoru sa ugradjenim centralnim horizontalnim reflektorom dobija veci fluks termalnih neutron pri istoj snazi i to utoliko veci ukoliko je moderaciona sposobnost aktivne zone manja. Pored uvecanja termalne komponente neutrona u snopu na horizontalnim eksperimentalnim kanalima centralni reflektor uslovljava i smanjenje epitermalne komponente, kao i intenzitet gamma zracenja. Ovo je pozeljno za proucavanje (n,{gamma}) reakcija, neutron diffraction, etc.

  9. Planning the RA reactor fuel exchange - Task 3.08/03; Zadatak 3.08/03 - Planiranje izmene goriva reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Dobrosavljevic, N; Strugar, P [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    From the reactor start-up until January 1963, after reactor operation of 1246 MWd , there was a need for fuel exchange. It was necessary to develop a method for planning the refuelling scheme which would enable economic and most appropriate further operation. The most suitable scheme for refuelling would be continuous exchange, but this cannot be performed since each fuel exchange demand reactor shutdown of approximately 15 days. For that reason a compromise scheme was adopted, meaning the fresh fuel is added after each 60-80 days of operation. This report describes the method for approximate calculation of reactivity increase during exchange of the spent fuel element with the fresh one. Detailed plan for exchange of fuel exchange is given in the conclusions.

  10. Operation and maintenance of the RA reactor in 1964, I-II, Part I; Pogon i odrzavanje reaktora RA u 1964. godini, I-II, I Deo

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    During 1964, the Reactor as operated about 20 days each months at nominal power of 6.5 MW, 5 days at lower power levels and 5 days were used for maintenance. Total production was 27930 MWh which is 11.7% higher than the planned value. Fuel exchange was done 3 times during this period, 98 spent fuel channels were exchanged. In addition to routine maintenance of reactor components and instruments a series of analyses of heavy water and helium were done. Special attention was devoted to corrosion analyses of the reactor materials because of the heavy water system was refurbished decontaminated in 1963. Utilization of the experimental space in the reactor was better that previously. 546 samples were irradiated till the end of November, of which 443 for users from the Institute. Specific irradiations in the fast neutron flux were done in six VISA-2 channels in the core.

  11. Determining axial perturbation of the reactor cell by introducing construction material into reactor fuel element; Odredjivanje aksijalne perturbacije celije unosenjem konstrukcionog materijala u gorivni element nuklearnog reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Dimitrijevic, V [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1975-07-01

    Axial distribution of thermal neutrons in the center and on the surface of a fuel element in the presence of aluminium was measured by reactor cell perturbation method. Experiments were performed by Dy activation foils using 20 mm thick Al disc placed between two fuel elements. Measured values of thermal neutron flux distribution in the reactor cell were compared to calculated values obtained by one-group neutron diffusion method.

  12. WWER-440 reactor emergency cooling using `feed and bleed` procedure; Avarijnoe raskholazhivanie reaktora WWER-440 s pomoshtyu protsedury `podpitka-produvka`

    Energy Technology Data Exchange (ETDEWEB)

    Marinov, M; Dimitrov, B; Popov, E; Avdzhiev, K [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    A procedure for emergency cooling in the case of total loss of coolant water is proposed. `Feed and bleed` procedure is applied by the operator and its main goal is to maintain a predefined level in the primary circuit and low pressure and temperature in the reactor. Two extreme cases are considered: 1. the loss of coolant is combined with a blackout; 2. the loss of feeding water is due to a general failure in the control room. The accidents are simulated and the relevant time intervals are estimated. After a simulated operator action following the procedure the reactor temperature is evaluated to 147{sup o} C and the primary circuit pressure to 10 bar. 1 ref., 4 figs., 2 tabs.

  13. Safety analysis of RA reactor operation, I-III, Part II, Accident analysis; Analiza sigurnosti rada reaktora RA - I-III, II deo - Analiza akcidenta

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This volume covers the analyses of two types of accidents: accidents caused by uncontrolled reactivity increase, and accidents caused by decrease or loss of cooling. First type of accidents, uncontrolled reactivity insertion could occur due to removal of compensation, regulatory or safety rods, or by increase of heavy water level. Removal of irradiated samples from the core could also cause increase of reactivity. Second type of accidents could occur due to interruption of cooling, loss of water in the secondary cooling loop or loss of water in the primary coolant loop.

  14. Nuclear reactors sources of contamination - RA reactor in Vinca as an example; Nuklearni reaktori kao izvori kontaminacije - Primer reaktora RA u Vinci -

    Energy Technology Data Exchange (ETDEWEB)

    Mitrovic, S; Djukic, Z; Dobrosavljevic, N [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-03-15

    This study contains an analysis of possible contamination caused by reactor accidents. In addition to description of maximum credible accident impacts on the environment it covers the prevention and procedures to be undertaken in case of accident. The RA reactor was taken as an example. Since the probability of maximum credible accident is very low minor accident that could cause fission products release were analyzed. Analysis of the spent fuel storage pool at the RA reactor is included as well.

  15. Report of the Service for maintenance of electric equipment Service - Annex 3; Prilog 3 - Rad sluzbe za odrzavanje elektro opreme reaktora RA u 1975. godini

    Energy Technology Data Exchange (ETDEWEB)

    Stamenkovic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period. [Serbo-Croat] Ovaj izvestaj opisuje organizaciju rada sluzbe za kontrolu i odrzavanje elektro-opreme i sadrzi detaljne podatke o potrosnji elektricne energije, smetnjama u napajanju elektricnom energijom, kvarovima u proteklom periodu.

  16. The analysis of the RA reactor irradiated fuel cooling in the spent fuel pool; Analiza hladjenja ozracenog goriva u bazenu za odlaganje reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Vrhovac, M; Afgan, N; Spasojevic, D; Jovic, V [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1985-07-01

    According to the RA reactor exploitation plan the great quantity of the irradiated spent fuel will be disposed in the reactor spent fuel pool after each reactor campaign which will including the present spent fuel inventory increase the residual power level in the pool and will soon cause the pool capacity shortage. To enable the analysis of the irradiated fuel cooling the pool and characteristic spent fuel canister temperature distribution at the residual power maximum was done. The results obtained under the various spent fuel cooling conditions in the pit indicate the normal spent fuel thermal load even in the most inconvenient cooling conditions. (author)

  17. Operation and maintenance of the RB reactor, Annual report for 1977; Pogon i odrzavanje reaktora RB, Izvestaj o radu u 1977. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1977-07-01

    The annual report for 1977 includes the following: utilization of the RB reactor; new regulations and instructions for reactor operation; improvement of experimental possibilities of the RB reactor; state of the reactor equipment; dosimetry and radiation protection; reactor staff. Five annexes are concerned with: testing the properties of preamplifiers for linear and logarithmic experimental channels; properties of the neutron converter; maintenance of the reactor equipment; purchase of new equipment; and the program for training reactor operators.

  18. Annex 1 - Task 08/12 final report, testing the RA reactor fuel element; Prilog 1 - Zavrsni izvestaj o podzadatku 08/12, Ispitivanje gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Mihajlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Testing of the RA reactor fuel element is presented in Annex 2 and 3 of this report. Annex 2 describes the construction of individual parts of the fuel elements and the results of the chemical analyses. Annex 3 shows the microstructure of uranium in the fuel element.

  19. Operation and maintenance of the RA reactor in 1964, I-II, Part II; Pogon i odrzavanje reaktora RA u 1964. godini, I-II, II Deo

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    This volume of the report contains the following 15 Annexes: Improvement of the fuel cycle economy (record No. 37009803 in INIS DB); Analysis of neutron flux increase in horizontal experimental channels of the RA reactor record No. 37005698 in INIS DB); Application of the critical system for determining the thermal neutron flux in a research reactor with central horizontal reflector ( record No. 37055005 in INIS DB); Determining the capacity of the RA reactor heat exchanger dependent on the coolant water temperature and flow; Operation of the RA reactor in forced regime; Analysis of the CEN-132 heavy water pumps failures at the RA reactor from decontamination till present; Modifications in the vacuum loop of the distillation system; Report on decontamination of the evaporator and cleaning of the condenser of the distillation system; Operation of reactor at nominal power with reduced D{sub 2}O circulation; Cooling of the RA reactor with reduced flow rate in the heavy water loop; Measurement of the heavy water level in the fuel channels of the RA reactor; Conclusions of the experts group of the RA reactor at the meeting held on November 2 and 3 1964; Conclusions of the experts group at the meeting held on November 23 1964; After heat and the cooling problem after RA reactor shut-down; Measurement of noise and vibrations on the Ra reactor heavy water system; Calculation and measurement of the uranium temperature during irradiation in the experimental channel in the reflector of the RA reactor; Temperature measurement of the reactor materials samples irradiated in the fuel channels of the RA reactor; Study of the modifications in the synchronous generators, heavy water pumps and condenser batteries of the RA reactor.

  20. Identification of mechanical vibrations in a PWR reactor using neutron noise signal analysis of the standard instrumentation; Identifikacija mehanichkih varijacija analizom signala shuma standardne neutronske instrumentacije PWR reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Kostic, Lj [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia); Runkel, J [Institut fuer Kerntechnik und Zerstoerungsfreie Pruefverfahren, Hannover (Germany)

    1988-07-01

    The neutron noise signals in a PWR power plant were analysed in terms of auto- and cross-power spectral densities, phases and coherences. Core barrel motion, fuel element vibrations and reactivity noise effect due to pressure variations have been monitored and analysed. (author)

  1. Calculation of physical and thermo hydro-dynamic parameters of a thermal research reactor; Prorachun fizichkih i toplotno hidro-dinamichkih parametara termichkog istrazhivachkog reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Matausek, M; Spasojevic, D; Jovic, V; Marinkovic, N [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

    1988-07-01

    The paper presents initial activities on creating a design concept of a new thermal research reactor, which should be built according to the research and development program in the field of nuclear fuel cycle technologies. For one possible type of such a reactor basic design parameters are specified and some preliminary results of nuclear, thermal and hydrodynamic design calculations are given. (author)

  2. Perturbation method for experimental determination of neutron spatial distribution in the reactor cell; Metoda perturbacije za eksperimentalno odredjivanje prostorne raspodele neutrona u celiji reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Takac, S M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1972-07-01

    The method is based on perturbation of the reactor cell from a few up to few tens of percent. Measurements were performed for square lattice calls of zero power reactors ANNA, NORA and RB, with metal uranium and uranium oxide fuel elements, water, heavy water and graphite moderators. Character and functional dependence of perturbations were obtained from the experimental results. Zero perturbation was determined by extrapolation thus obtaining the real physical neutron flux distribution in the reactor cell. Simple diffusion theory for partial plate cell perturbation was developed for verification of the perturbation method. The results of these calculation proved that introducing the perturbation sample in the fuel results in flattening the thermal neutron density dependent on the amplitude of the applied perturbation. Extrapolation applied for perturbed distributions was found to be justified.

  3. RA reactor reactivity changes before refurbishment - Task 3.08/02; Zadatak 3.08/02 - Promene reaktivnosti reaktora RA do remonta

    Energy Technology Data Exchange (ETDEWEB)

    Dobrosavljevic, N; Strugar, P; Stamenkovic, S [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    From the the end of 1959, when the RA reactor started operation until January 1963 reactor was operated with the initial fuel batch of 56 fuel channels. After 310 MWd 68 fuel channels were added to the reactor core, and after further 357 MWd the core was filled up to the maximum of 88 fuel channels. Basic reactor parameters were systematically measured during two years of operation. This report covers the measurements concerned directly with the reactor operation: calibration of the control rods and their reactivity worths during operation, determining the total built-in reactivity excess and its change during burnup, determination of reactivity dependence on the temperature, xenon effect in the core.

  4. Regulations and instructions; Propisi i uputstva

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    Regulations and instructions for operating the RA reactor consist of the following chapters: general regulations with the fundamental RA reactor characteristics, operating regulations and instructions for the personnel on duty, regulations for accidental conditions, training program for the staff of the Laboratory for reactor operation. Propisi i uputstva za rad reaktora RA sadrze sledeca poglavlja: opsti deo sa kratkim opisom karakteristika reaktora RA, propisi za rad dezurnog osoblja, propisi za slucaj udesa, program obuke osoblja Laboratorije za eksploataciju reaktora RA.

  5. I-1 General; I-1 Opsti deo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    General part of the regulations and instructions for operation of the RA reactor includes fundamental data about the reactor properties, biological shields, purpose of reactor operation, organizational scheme, rights and responsibilities of the head of laboratory, leaders of the working teams and all the staff of the laboratory for RA reactor exploitation. Opsti deo knjige propisa i uputstva za rad reaktora sadrzi osnovne podatke o reaktoru, biloskoj zastiti, nameni reaktora, prava i duznosti nacelnika, sefova smena i osoblja laboratorije za eksploataciju reaktora RA.

  6. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels. [Serbo-Croat] Ovo (prvo) poglavlje sadrzi sledece: Opis reaktora RA; semu organizacije rada i rukovodjenja; prava i duznosti direktora i rukovodioca pogona reaktora, propise o rezimu rada i kretanja u zgradi reaktora, propise o izvodjenju eksperimenata, propise o unosenju uzoraka u eksperimentalne kanale reaktora.

  7. Report of the Service for maintenance of mechanical structures - Annex 2; Prilog 2 - Rad sluzbe za odrzavanje masinske opreme

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    This Annex 2 describes the organizational structure and activities of the Service for maintenance of the mechanical structures of the RA reactor, inspection and maintenance of of reactor components, workshop and storage of spare parts at the reactor. Mechanical structures of the RA reactor included are: heavy water system, gas systems, technical water system, reactor core, and transportation equipment. [Serbo-Croat] Pored opisa organizacije rada sluzbe za odrzavanje masinske opreme reaktora RA, ovaj prilog sadrzi: podatke o stanju, reviziji i remontu masinske opreme reaktora RA, prirucne radionice i magacina. Masinska oprema reaktora RA obuhvata: sistem teske vode, gasne sisteme, sistem tehnicke vode, centralno telo reaktora, transportnu opremu.

  8. Tasks related to increase of RA reactor exploitation and experimental potential, 02. Verification of the system for detecting failures of the RA reactor fuel element cladding; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 02. Provera sistema za detekciju pucanja kosuljice gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    For the purpose of this task it was necessary to analyze the time dependent distribution of fission products in the fuel element and leaks through the cracks in the cladding; to calculate the quantity of solid fission products, volatile fission products and fission gases for the RA reactor; to collect the data for estimating the activity of the short-living isotopes created by neutron irradiation of D{sub 2}O; analyze the number of delayed neutrons in D{sub 2}O. Experiment were needed to estimate the distribution of Xe and Kr in the heavy water in the reactor channel and analyze the activity of D{sub 2}O and helium based on reactor operation data. For the purpose of verifying the efficiency and safety of the existing system for detecting the cracks of the fuel element cladding is presented in this report together with the review of similar systems at a number of reactors in the world.

  9. Measuring set: Reactor Power Meter (type of SG-8), Reactor Energy Meter (type of SG-11) and Digital Dose Meter (type of SG-9) for reactor rigs operation. Zestaw pomiarowy: miernik mocy reaktora (typ SG-8), miernik energii reaktora (typ SG-11) oraz cyfrowy miernik dawki (typ SG-9) dla potrzeb eksploatacji sond reaktorowych

    Energy Technology Data Exchange (ETDEWEB)

    Glowacki, S W

    1982-01-01

    A measuring set consisting of the Reactor Power Meter, Reactor Energy Meter and Digital Dose Meter is described. The gamma radiation of water in the reactor primary cooling circuit reaches the ionisation chamber and involves the output current, driving the Reactor Power Meter and Reactor Energy Meter. The Digital Dose Meter is controlled by the output current of the self-powered detector mounted inside the reactor rig.

  10. Tasks related to increase of RA reactor exploitation and experimental potential, 01. Designing the protection chamber in the RA reactor hall for handling the radioactive experimental equipment (I-II) Part II, Vol. II; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 01. Projektovanje zastitne komore u hali reaktora RA za rad sa aktivnim eksperimentalnim uredjajima (I-II), II Deo, Album II

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    This second volume of the project for construction of the protection chamber in the RA reactor hall for handling the radioactive devices includes the technical description of the chamber, calculation of the shielding wall thickness, bottom lead plate, horizontal stability of the chamber, cost estimation, and the engineering drawings.

  11. Tasks related to increase of RA reactor exploitation and experimental potential, 03. Crane for handling the vertical experimental channels of the RA reactor - design project; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 03. Kran za opsluzivanje vertikalnih eksperimentalnih kanala reaktora RA - izrada projekta

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    Within the work related to improvement of experimental potential of the RA reactor, this document describes the design project of the new crane for handling the vertical experimental channels of the RA reactor, engineering drawings of the crane main elements, mechanical part, design project of the electrical part of the crane and cost estimation.

  12. Tasks related to increase of RA reactor exploitation and experimental potential, 04. Device for transport of radioactive reactor channels and semi channels of the RA reactor, design project (I-III) Part II, Vol. II; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 04. Uredjaj za transport aktivnih tehnoloskih kanala I semikanala reaktora RA - izrada projekta (I-III), II Deo, Album II

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    This second volume includes calculations of the main components of the transporter, description of the mechanical part of the transporter and the engineering drawing of the device for transport of radioactive reactor channels and semi channels of the RA reactor.

  13. The Use of Prestressed Concrete Vessels in the French Power Reactor Programme; Les caissons en beton precontraint dans le programme francais des reacteurs de puissance; Korpusy iz predvaritel'no napryazhennogo betona vo frantsuzskoj programme ehnergeticheskikh reaktorov; Empleo de recipientes de presion de hormigon pretensado en el programa frances de reactores de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Conte, F. [Centre d' Etudes Nucleaires de Marcoule (France); Dambrine, C. [Centre d' Etudes Nucleaires de Fontenay-aux-Roses (France); Gaussot, D. [Electricite de France, Clamart (France)

    1963-10-15

    de la pression de service et de toutes manieres, une augmentation notable des dimensions, ce qui permet d'envisager des solutions du type integre. (author) [Spanish] G3 de Marcoule y en el reactor EDF3, en construccion en Chinon. Los reactores se encuentran en servicio desde 1959 y 1960, respectivamente; el Comissariat a l'energie atomique indica los problemas que ha planteado la construccion de los recipientes de presion y las observaciones efectuadas durante el funcionamiento de los reactores, que ponen de manifiesto la gran seguridad de los mencionados recipientes. La construccion del recipiente de presion del reactor EDF3, que comenzo en Chinon en el segundo semestre de 1961, prosigue actualmente y quedara terminada a fines de 1963. L'Electricite de France expone los motivos de la eleccion de este tipo de recipiente, los resultados de los calculos y de los ensayos efectuados con maquetas, asi como los problemas planteados por sir construccion. Se han llevado a cabo varios estudios sobre las perspectivas del empleo del hormigon pretensado en los reactores. Al parecer, este material permite obtener un aumento de la presion de trabajo y de todas maneras, un incremento notable de las dimensiones, lo que a su vez permite tomar en consideracion soluciones de tipo integrado. (author) [Russian] Izlagaetsya vopros o primenenii predvaritel'no napryazhennogo betona dlya reaktorov G.2 i G.3 v Markule i dlya stroyashchegosya v Shinone reaktora EDF.3. Reaktory dostigli mosnosti sootvetstvenno v 1959 i 1960 godakh; KAEH otmechaet problemy, kotorye voznikli v protsesse stroitel'stva korpusa reaktora, i izlagaet filosofiyu nablyudenij, kotorye prodemonstrirovali vysokuyu bezopasnost' ehtikh ustanovok. K stroitel'stvu korpusa reaktora EDF.3 v SHinone pristupili vo vtoroj polovine 1961 goda; stroitel'stvo budet zaversheno k kontsu 1963 goda. ''Ehlektrisite de Frans'' ob{sup y}asnyaet prichiny vybora takogo korpusa, privodit rezul'taty raschetov i provedennykh na makete ispytanij, a

  14. Measurements of neutron flux in the RA reactor; Merenje karakteristika neutronskog fluksa u reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This report includes the following separate parts: Thermal neutron flux in the experimental channels od RA reactor; Epithermal neutron flux in the experimental channels od RA reactor; Fast neutron flux in the experimental channels od RA reactor; Thermal neutron flux in the thermal column and biological experimental channel; Neutronic measurements in the RA reactor cell; Temperature reactivity coefficient of the RA reactor; design of the device for measuring the activity of wire. [Serbo-Croat] Ovaj izvestaj sadrzi sledece referate: Fluks termalnih neutrona u eksperimentalnim kanalima reaktora RA; Fluks epitermalnih neutrona u eksperimentalnim kanalima reaktora RA; Fluks brzih neutrona u eksperimentalnim kanalima reaktora RA; Fluks termalnih neurona u termalnoj koloni i bioloskom eksperimentalnom kanalu; Neutronska merenja u elementarnoj celiji reaktora RA; Temperaturni koeficijent reaktivnosti reaktora RA; Projekat uredjaja za merenje radioaktivnosti zice.

  15. Materials Control in the Fabrication of Enriched Uranium Fuels; Controle des Matieres au Cours de la Fabrication des Combustibles a Base d'Uranium Enrichi; Uchet materialov pri izgotovlenii topliva na obogashchennom urane; Control de Materiales en la Elaboracion de Combustibles de Uranio Enriquecido

    Energy Technology Data Exchange (ETDEWEB)

    Cardwell, Jr., R. G. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1966-02-15

    densidad. La manipulacion de la chatarra tuvo una importante influencia en el balance de los materiales que confirmo el contenido de combustible y aseguro una buena contabilizacion. Los procedimientos de manipulacion y registro, y en particular los metodos de determinacion de las partidas y de marcacion fisica, se formularon de tal manera que constituyeron una buena ayuda para el fabricante en lo que respecta al control de la criticidad. (author) [Russian] Usilennaja dejatel'nost' v oblasti tehnologii teplovydeljajushhih jelementov, provodivshajasja v Okridzhskoj nacional'noj laboratorii na protjazhenii poslednih 15 let, privela k vyrabotke racional'nyh tehnologicheskih processov i metodov ucheta obogashhennyh materialov, kotorye sejchas shiroko primenjajutsja pri izgotovlenii teplovydeljajushhih jelementov v promyshlennom masshtabe. V hode proektirovanija i izgotovlenija prototipov teplovydeljajushhih jelementov dlja zapuska reaktora dlja ispytanija materialov, reaktora s massovoj zashhitoj ili {sup b}assejnovogo tipa{sup ,} kompaktnogo jenergeticheskogo reaktora voennogo obrazca, reaktora s bashennoj zashhitoj, pokazatel'nogo reaktora dlja Zhenevskoj konferencii, izotopnogo reaktora s potokom bol'shoj intensivnosti i jeksperimentol'nogo reaktora s gazovym ohlazhdeniem byli vyrabotany i prinjaty v kachestve ustanovlennyh norm nadezhnye metody obrashhenija s obogashhennym toplivom v vide splavov, suspenzii ili okisej. Nakoplennyj opyt posluzhil osnovoj dlja dannogo doklada, v kotorom podcherkivajutsja problemy ucheta materialov i ih razreshenie pri izgotovlenii razlichnyh sostavnyh chastej teplovydeljajushhih jelementov razlichnyh tipov na obogashhennom urane. Osnovnymi zadachami pri vyrabotke horoshej sistemy ucheta materialov javljajutsja: 1) sokrashhenie chisla edinic podotchetnogo materiala; 2) vyrabotka otdel'nyh uchetnyh dokumentov dlja kazhdoj vazhnoj stadii izgotovlenija i sostavlenie ih svodki sposobom, pozvoljajushhim s naimen'shej zatratoj truda vyjavljat' mesta

  16. Biomechanical analysis of skilled female gymnasts' motor actions in vaulting «rondat fllick» with the new table [Biomekhanicheskij analiz dvigatel'nykh dejstvij kvalificirovannykh gimnastok v opornom pryzhke tipa «rondat-fliak» na snariade «pryzhkovyj stol»

    Directory of Open Access Journals (Sweden)

    Khmelnitska I.V.

    2011-11-01

    Full Text Available Biomechanics descriptions of technique of motive actions of gymnasts are presented. 20 gymnasts took part in an experiment. The analysis of 72 appearances of gymnasts and 144 supporting jumps is conducted. Errors are considered in the technique of motive actions of gymnasts at implementation of supporting jumps. It is marked that frequency of the use of supporting jump «Rondat Fllick» among all of supporting jumps is 40 %. It is set that the leading elements of motive structure of technique are biomechanics descriptions of the second phase of flight (duration, height of flight and landing distance.

  17. ASSOTsIATsIYa GENETIChESKOGO POLIMORFIZMA GENOV RETsEPTORA VITAMINA D (VDR, KOLLAGENA AI TsEPI KOLLAGENA A I TIPA (COL1A1, I FAKTORA NEKROZA OPUKhOLE-A (TNFA I SOSTOYaNIYa MINERALIZATsII SKELETA U DETEY S BOLEZN'Yu KRONA

    Directory of Open Access Journals (Sweden)

    TV GABRUSSKAYa

    2016-08-01

    Full Text Available Болезнь Крона (БК - тяжелое аутоиммунное заболевание желудочно-кишечного тракта, влияющее на качество жизни, развитие ребенка и характеризующееся высоким риском инвалидизации. Изменения состояния костной ткани у пациентов с БК являются нередкими и проявляются задержкой линейного роста, снижением показателей минерализации скелета, изменениями костного метаболизма, повышенным риском низкоэнергетических переломов. Изменения костной ткани обусловлены сочетанием факторов болезни (мальабсорбция, терапия кортикостероидами, дефицит витамина D, низкая двигательная активность, дефицит инсоляции, задержка полового развития и генетических факторов, регулирующими костный метаболизм. Цель: проанализировать наличие ассоциации между показателями костного метаболизма и носительством полиморфных генетических маркеров генов VDR, COL1A1, TNFa. Материал и методы. В исследование включено 44 ребенка с БК (25 мальчиков и 19 девочек в возрасте от 3 до 17 лет. Исследование минерализации скелета осуществлялось методом двуэнергетической рентгеновской абсорбциоме-трии поясничного отдела позвоночника L1-L4 (денситометр Hologic QDR 4500C, оснащенный педиатрической референтной базой. Молекулярно-генетические исследования: определение 1546G/T полиморфизма гена al цепи коллагена I типа (COL1A1, TaqI полиморфизма гена рецептора витамина D (VDR, -308G/A полиморфизм гена фактора некроза опухолей-a (TNF-a осуществлялось методом полимеразной цепной реакции с последующим рестрикционным анализом. Оценивались показатели минеральной плотности кости (МПК, оцениваемые при помощи Z критерия (МПК-Zscore, дефицит МПК в процентах, частота низкой МПК (НМПК, которая определялась как МПК-Zscore < - 2 SD. Результаты. При изучении частот распределения полиморфных генотипов изученных генов у детей с НМПК и без, не было выявлено достоверных различий в общей группе, а также среди мальчиков и девочек. В показателях МПК-Zscore среди носителей TaqI полиморфных генотипов гена VDR в общей группе (р=0,51, группе мальчиков (р=0,7 и девочек (р=0,68. Среди носителей полиморфных 1546G/T генотипов гена (COL1A1 также не было выявлено различий в показателях МПК-Zscore в общей группе (р=0,79, группе мальчиков (р=0,42 и девочек (р=0,95. При изучении ассоциации -308 G/A полиморфизма гена TNF-a выявлено, что, пациенты, носители гетерозиготного генотипа m/n по сравнению с носителями гомозиготного генотипа n/n имели более низкие показатели МПК: МПК-Zscore = -2,35 SD (-3,4; -1,35 и -1,4 SD (-2,3; -0,5, p=(0,1, соответственно и дефицит МПК: -28,0% (-43,0; -15,5 и -11,5% (-22,5; -6,0, (р=0,034, соответственно Выводы. Выявлена ассоциация гетерозиготного полиморфного генотипа m/n гена -308 G/A TNF-a с более выраженными нарушениями МПК у детей с БК. Требуется продолжение исследований для уточнения роли полиморфных маркеров генов в реализации нарушений МПК у детей с БК.

  18. Probabilistic safety analysis of the Kozloduy NPP units 1-4 (WWER-440/230) using independent emergency feedwater system; Veroyatnostnyj analiz bezopasnosti I-IV blokov AEhS `Kozloduy` s reaktorami tipa WWER-440 (V 230) pri vklyuchenii nezavisimoj sistemy avarijnoj podpitki PG

    Energy Technology Data Exchange (ETDEWEB)

    Kalchev, B; Marinov, M; Dimitrov, B; Avdzhiev, K [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    The safety of the Kozloduy NPP is being promoted by backfitting and improved operational practice. Special measures mitigating potential severe accidents consequences are needed because of some deficiencies in the original design of the four WWER-440 units. In conditions of a total LOCA (Loss Of Coolant Accident) it is impossible to ensure decay heat removal using the existing safety system. In such cases an extra emergency feedwater system independent of the plant`s other systems has been introduced which offers a new alternative means of removing the residual heat from the reactor. A probabilistic safety analysis is carried out using the method of event trees. A comparison between the existing safety system and the newly proposed is made. The simulation results of the unit behaviour prove that the damage frequency of the active zone is lower with the new system. 3 refs., 3 tabs., 2 figs.

  19. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

  20. RA Reactor operation and maintenance (I-IX), Part III, Task 3.08/04-02 Refurbishment of the electrical equipment; Pogon i odrzavanje reaktora RA (I-IX), III Deo, Zadatak 3.08/04-02 Remont elektro opreme

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Nikolic, M; Poznanovic, B; Rajic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This volume contains detailed action plan for repair of electrical equipment of the RA reactor, the list of electrical equipment parts which were either repaired or exchanged for improvement of their performance. Detailed work describing the repair and maintenance work done of the listed equipment is part of this report. Equipment related to dosimetry and control systems are included as well.

  1. Control of the working environment dosimetry and technical radiation protection at the RA reactor, Part I; Deo I: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, N; Bjelanovic, J; Minicic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 16.9 mSV during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the permissible annual exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1984. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel.

  2. RA Research nuclear reactor, Part II - radiation protection at the RA nuclear reactor in 1984; Istrazivacki nuklearni reaktor RA - Deo II - zastita od zracenja kod nuklearnog reaktora RA u 1984. godini

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Ajdacic, N; Zaric, M; Vukovic, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    Radon protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Collecting and treatment of fluid effluents; and (4) radioactive wastes, decontamination and actions. Each category is described as a separate annex of this report.

  3. RA Reactor operation and maintenance (I-IX), Part II, Task 3.08/04; Pogon i odrzavanje reaktora RA (I-IX), II Deo, Zadatak 3.08/04

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Repair and maintenance work of the RA reactor components and equipment was longer than planned due to the following reasons: chemical decontamination of the reactor heavy water system indispensable for maintenance of the heavy water pumps; findings of contamination origin changed the maintenance schedule; some construction materials of the heavy water pumps which caused contamination had to be removed; a number of the planned operations had to be performed under increase level of gamma radiation which increased the time needed for repair. This report covers detailed description of all the maintenance and repair work done from 25 Jan to 22 Apr 1963.

  4. Graphical method for determination of critical dimensions and neutron flux distribution in multi zone nuclear reactors; Graficka metoda za odredjivanje kriticnih dimenzija i raspodele fluksa kod multiregionalnih nuklearnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Radanovic, Lj; Bingulac, S; Lazarevic, B; Matausek, M [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    This paper describes the graphical method for calculating the neutron flux distribution by using normalized Riccati equations. It was shown that the solutions of adequately normalized Riccati equations could be used as standard curves for determining the critical dimensions and radial flux distribution in multi zone nuclear reactors. the methos is applicable irrelevant of the number and position of the region in the core.

  5. Operation and maintenance of the RA reactor, Report on operation in 1966, task 6.08; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1966. god. Zadatak 6.08

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D and others [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-12-15

    During 1966, RA reactor was operated at nominal power for 196 days and 28 days at lower power levels. The total production was 31015 MWh which is 3% higher than planned. Practically there were no discrepancies from the plan. The reactor was used for irradiation and experiments according to the demand of 644 users, of which 516 were from the Institute. This report contains detailed data about reactor power and experiments performed in 1966, and a chart showing discrepancies from the plan. data concerned about the utilization of reactor experimental channels are included as well. Total number of safety shutdowns was 37, of which 20 were caused by power cuts, 10 due to voltage instabilities, 4 due to human error and 3 due to failures of instrumentation. These data are compared to safety shutdown data of previous few years. There have been no accidents which could cause any significant effects. The incidents occurred during this year are described in detail. Detailed data concerning exposure of the personnel are part of this report.

  6. Operation and maintenance of the RA reactor, Report on operation in 1967, task 7.08; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1967. god. Zadtak 7.08

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D and others [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1967-12-15

    During 1967, RA reactor was operated at nominal power for 190 days and 23 days at lower power levels. The total production was 31060 MWh. Report contains data until Dec. 22. 1967, but the reactor was planned to operate three more full days at nominal power of 6.5 MW, meaning that the total number of operation at full power would be 193 days ant the total production would be 30625 which is 2% higher than planned. Practically there were no discrepancies from the plan. There have been 5 shorter interruptions in operation caused by demand of the experiment, minor repairs and thunderstorm. Only one longer interruption was caused by difficulties in secondary water supply. The reactor was used for irradiation and experiments according to the demand of 590 users, of which 470 were from the Institute. This report contains detailed data about reactor power and experiments performed in 1967, and a chart showing discrepancies from the plan. Data concerned about the utilization of reactor experimental channels are included as well. Total number of safety shutdowns was 19, of which 11 were caused by power cuts, 6 due to voltage instabilities, and 2 due to failures of instrumentation. These data are compared to safety shutdown data from 1962 - 1967. There have been no accidents which could cause any significant effects. The only important incident occurred this year was caused by leaking of sulphur from an experimental capsule. It is described in detail. Detailed data concerning exposure of the personnel are part of this report. In spite of the fact that this year the spent fuel was for the first time packed and mixing of the fuel in the core there have been no unplanned difficulties nor contaminations.

  7. From a critical assembly heavy water - natural uranium to the fast - thermal research reactor in the Institute Vinca; Od kriticnog sistema teska voda - prirodni uranium do brzo - termickog istrazivackog reaktora u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovic, D; Pesic, M [Vinca Institute of Nuclear Sciences, Beograd (Yugoslavia)

    1995-07-01

    A part of the Institute in Vinca this monograph refers to is the thermal nuclear zero power reactor RB, with a heavy water moderator and variously enriched uranium fuel, that is, its present day version, the coupled fast-thermal system HERBE. A group of research workers, technicians, operators and skilled workmen in the workshop have worked continuously on it. Some of them have spent their whole working age at the reactor, and some a part of it. There is about a hundred and fifty internationally published papers, twenty master's and fourteen doctor's theses left behind them for the past thirty five years. This book is devoted to them. The first part of the text refers to the pioneering efforts on the reactor and fundamental research in reactor physics. The experimental reactor RB was designed and constructed at the time to operate with natural uranium and heavy water. Measurements are presented and the first results of reaching critical state, measurements of migration length of thermal neutrons and neutron multiplication factor in an infinite medium; also measurements of neutron flux density distribution and reactor parameter, and in the domain of safety, measurement of safety rods reactivity. Those were also the times when the known serious accident occurred with the uncontrolled rise of reactivity, which was especially minutely described in a publication of the International Atomic Energy Agency from Vienna. Later on, new fuel was acquired with 2 % enriched uranium. A series of experiments in reactor and neutron physics followed, with just the most interesting results of them presented here. In the period which followed, another type of fuel was available, with 80 % enriched uranium. New possibilities for work opened. Measurements with mixed lattices were performed, and the RA reactor lattices were simulated. After measurements mainly in the sphere of reactor and neutron physics, a need for investigations in the field of gamma and neutron radiation protection arose. While the RB reactor system was purely thermal with a variable neutron reflector, possibilities for this kind of research were comparatively limited. However, these possibilities were greatly increased by system configurations which had neutron converters built into them, and which created significant and spacious fast neutron fields suitable for various experiments. In the beginning of the eighties at the Institute in Vinca, designing and construction of a fast zero power reactor called LASTA began. The design was completed, location for it examined and arranged. In a mid-phase, even the main design of a subcritical system called MALA LASTA was also elaborated. RB reactor has its role in these designs, which consisted mostly of creation of neutron fields similar to the energy spectrum like the one in the LAST A, intended for basic measurements and acquiring of experimental experience for future experiments. In order to fulfil this task, a hybrid coupled fast-thermal system HERBE was completed, which will, in view of its significance, be devoted a part of this monograph. Reactor RB began its operation as part of the Laboratory for Physics and Dynamics of the Reactor. It was also a Basic Organization of Associated Labour, and now the Nuclear Engineering Laboratory developed around it. All the important data on this several-decades long work are presented in this monograph. (author)

  8. Determination of fine neutron flux distribution in multi-region reactor cell by applying spherical harmonics method; Odredjivanje fine rspodele fluksa u viseregionalnoj celiji reaktora primenom metode sfernih harmonika

    Energy Technology Data Exchange (ETDEWEB)

    Jockovic, M; Stefanovic, D; Barucija, M [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Neutron distribution in space, direction of movement, energy and time is described by Boltzmann equation. This paper describes the adaptation of method for calculating the neutron flux distribution in P{sub 3} approximation and the computer code written for the ZUSE-Z-23 computer. Some results for a few typical reactor cells are included. The number of regions in the reactor cell treated by the code is limited only by the capacity of the computer.

  9. Calculation of the fine neutron flux distribution in the multi-zone reactor cell by spherical harmonics method; Odredjivanje fine raspodele fluksa u viseregionalnoj celiji reaktora primenom metode sfernih harmonika

    Energy Technology Data Exchange (ETDEWEB)

    Jockovic, M; Stefanovic, D; Barucija, M [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-07-01

    This presentation contains development and application of method for calculating the neutron flux distribution by P{sub 3} approximation. A computer codes was developed for the ZUSE-Z-23 computer. Some typical results are included.

  10. Activity of the Service for maintenance of RA reactor electrical equipment in 1976, report - Annex III; Prilog III - Rad sluzbe za odrzavanje elektro opreme reaktora RA u 1976. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Stamenkovic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period. [Serbo-Croat] Ovaj izvestaj opisuje organizaciju rada Sluzbe za kontrolu i odrzavanje elektro-opreme i sadrzi detaljne podatke o potrosnji elektricne energije, smetnjama u napajanju elektricnom energijom, kvarovima u proteklom periodu.

  11. Dosimetry and technical radiation protection at the RA Reactor - Report for 1977, Annex V; Prilog V - Dozimetrija i tehnicka zastita od zracenja kod reaktora RA - Izvestaj za 1977. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1977-12-15

    This report includes data about the level of gamma and neutron radiation, and level of contamination in the working environment at the RA reactor, data about collective and individual exposure of the staff to radiation, data about contamination and decontamination as well as radioactive waste. During 1977, at the RA reactor there was no accident that would cause significant exposure of tf the staff or contamination of the working space and the environment of the reactor. [Serbo-Croat] Ovaj Izvestaj sadrzi podatke o nivou gama i neutronskog zracenja i stepenu kontaminacije radne sredine, podatke o individualnom i kolektivnom izlaganju zracenju radnog osoblja, podatke o kontaminaciji i dekontaminaciji kao i o radioaktivnom otpadu. U toku 1977. godine, na reaktoru RA nije bilo akcidenata vecih razmera koji bi za posledice imali znacajnije ozracivanje radnog osoblja i kontaminaciju radne sredine i okoline.

  12. Activity of the Service for maintenance of RA reactor electrical equipment in 1978, report - Annex III; Prilog III - Rad sluzbe za odrzavanje elektro opreme reaktora RA u 1978. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Stamenkovic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period. [Serbo-Croat] Ovaj izvestaj opisuje organizaciju rada Sluzbe za kontrolu i odrzavanje elektro-opreme i sadrzi detaljne podatke o potrosnji elektricne energije, smetnjama u napajanju elektricnom energijom, kvarovima u proteklom periodu.

  13. Monte Carlo estimation of the influence of elastic scattering anisotropy on the neutron flux in a nuclear reactor cell; Monte Carlo procena uticaja anizotropije elasticnog rasejanja na vrednost neutronskog fluksa u celiji nuklearnog reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Kocic, A [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1974-07-01

    Anisotropy of neutron elastic scattering is a problem of special importance in solving the Boltzmann transport equation numerically. This is not the case when Monte Carlo method is applied. Estimation of the influence of elastic scattering anisotropy on the neutron flux is treated in order to justify the application of Monte Carlo method which is computer time consuming. Correlation procedure was applied for the study of this influence. One group case was used as an example to enable comparison of other methods.

  14. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1984; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1984. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    During the 1984 the reactor operation was limited by the temporary operating license issued by the Committee of Serbian ministry for health and social care. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. This temporary license has limited the reactor power to 2 MW from 1981. Operation of the primary cooling system was changed in order to avoid appearance of the previously noticed aluminium oxyhydrate on the surface of the fuel element claddings. The new cooling regime enabled more efficient heavy water purification. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1984, three major tasks are planned: building of the new emergency system, reconstruction of the existing ventilation system, and renewal of the reactor instrumentation. Financing of the planned activities will be partly covered by the IAEA. this Part I of the report includes 8 Annexes describing in detail the reactor operation, and 6 special papers dealing with the problems of reactor operation and utilization.

  15. Annex 7 - Task 08/32 final report, Diffusion bond between the fuel and cladding of the RA reactor fuel element; Prilog 7 - Zavrsni izvestaj o podzadatku 08/32, Difuziona veza goriva i kosuljice gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Kustudic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Based on testing the diffusin bond between the fuel and the aluminium cladding of the RA reactor fuel element it was found that the diffusion bond exists; uranium is protected by a nickel layer to prevent the damaging diffusion between uranium and aluminium; the nickel layer is about 5 microns thick. Under assumption that the diffusion annealing was done after cladding the annealing temperature was about 500 deg C for about 1 hour.

  16. Measurement of thermal neutron spectrum by chopper at the RA reactor in the 'Boris Kidric' Institute; Merenje termickog neutronskog spektra iz reaktora RA u Institutu 'Boris Kidric' pomocu copera

    Energy Technology Data Exchange (ETDEWEB)

    Maglic, R [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1963-04-15

    Measurement of neutron spectrum described in this paper is one of the first measurements of neutron energy distribution at the reactor by time-of-flight method performed in our Institute. Measurement was done by applying the mechanical spectrometer (chopper) designed and constructed in 1961. Spectrometer was calibrated at the end of 1962.

  17. Study of reactor parameters of on critical systems, Phase I: Safety report for RB zero power reactor; Ispitivanje reaktorskih parametara na kriticnim sistemima, I faza: Izvestaj o sigurnosti reaktora nulte snage RB

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1962-09-15

    In addition to the safety analysis for the zero power RB reactor, this report contains a general description of the reactor, reactor components, auxiliary equipment and the reactor building. Reactor Rb has been reconstructed during 1961-1962 and supplied with new safety-control system as well as with a complete dosimetry instrumentation. Since RB reactor was constructed without shielding special attention is devoted to safety and protection of the staff performing experiments. Due to changed circumstances in the Institute ( start-up of the RA 7 MW power reactor) the role of the RB reactor was redefined.

  18. Study of the modifications on the synchronous generators, heavy water pumps and condenser batteries of the RA reactor - Annex 17; Prilog 17 - Elaborat o izmenama u semama sinhronih generatora, teskovodnih pumpi i kondenzatorskih baterija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    Modifications done on the synchronous generators are related to the emergency power supply system, meaning one of the most important devices responsible for reactor safety. Without reducing the efficiency of the heavy water pumps the improved stability of generators operation was achieved by reducing the possibility of errors and simplifying manipulation. Condensator batteries were improved in order to decrease the leakage currents.

  19. Testing of the fuel element - radiation damage of the construction materials of the fuel element and reactor core; Ispitivanje gorivnog elementa - radijaciono ostecenje konstrukcionih materijala gorivnog elementa i jezgra reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    This report covers the following: review of present radiation damage testing of stainless steels and zircaloy-2 used in heavy water reactors; plan of experiments for irradiation of of these materials.

  20. Activities of the Service for maintenance of the RA reactor electronic equipment in 1979 - Report - Annex IV; Prilog IV Rad sluzbe za odrzavanje elektronske opreme reaktora RA u 1979. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1979-12-15

    Within the organizational structure of the RA reactor staff, the Service for instrumentation maintenance has the following tasks: maintenance of the existing electronic equipment; participating in experiments planning and preparation of electronic equipment; purchasing new equipment, spare parts and components; construction of new equipment for internal needs; implementation of new equipment. Basic instrumentation of the reactor facility includes: control and protection system, and dosimetry system. [Serbo-Croat] U okviru organizacione seme OOUR nuklearni reaktor RA sluzba za odrzavanje instrumentacije postrojenja ima sledece zadatke: odrzavanje postojece elektronske opreme; ucesce u planiranju eksperimenata i priprema elektronske opreme; nabavka nove opreme, rezervnih delova i komponenti; rad na izradi elektronske opreme i uredjaja za sopstvene potrebe i izrada projekata u domenu reaktorske opreme i ucesce u ugradnji nove opreme. Osnovna instrumentacija postrojenja obuhvata: sistem za upravljanje i zastitu, sistem za tehnolosku kontrolu i sistem za dozimetrijsku kontrolu.

  1. Theoretical analysis of nuclear reactors (Phase II), I-V, Part IV, Depletion of nuclear fuel; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, IV Deo, Promena izotopnog sastava goriva

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    This phase of the project deals with the U{sup 238} isotope chain with the analysis of Pu{sup 239} build-up. Part one of the report shows two theoretical approaches, one leading to a system of differential equations which could be solved by using a computer, and the second Machinari-Goto method which gives analytical expressions for approximations for certain isotopes. Part two includes the results obtained by using digital computer ZUSE-Z22-R.

  2. Development of methods for theoretical analysis of nuclear reactors (Phase II), I-V, Part IV, Fuel depletion; Razrada metoda teorijske analize nuklearnih reaktora (II faza), I-V, IV Deo, Promena izotopnog sastava goriva

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    This report includes the analysis of plutonium isotopes from U{sup 238} depletion chain. Two theoretical approaches for solving the depletion of fuel are shown. One results in the system of differential equations that can be solved only by using electronic calculators and the second, Machinari-Goto method enables obtaining analytical equations for approximative values of particular nuclei. In addition, differential equations are given for different approximation levels in calculating Pu {sup 239}, as well as relations between the released energy and irradiation. Ova faza obuhvata analizu stvaranja izotopa plutonijuma u lancu U{sup 238}. Prikazana su dva teorijska pristupa resavanju problema 'konverzije goriva', jedan dovodi do sistema diferecijalnih jednacina za cije je resavanje neophodno koriscenje elektronskih racunskih masina, i drugi, Machinari-Goto metod koji omogucava da se dobiju analiticki izrazi vrednosti aproksimacije pojedinih jezgara. Osim toga date su diferencijalne jednacine raznih stepena aproksimacije u racunanju Pu {sup 239}, kao i veze izmedju oslobodjene energije i ozracivanja.

  3. Mechanical neutron spectrometer Chopper - Experimental study of the neutron beam topography in the channel C of the 'A' reactor; Neutronski mehanicki spektrometar (coper) - Eksperimentalno odredjivanje topografije neutronskog snopa na kanalu 'C', reaktora 'A'

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, V [Institute of Nuclear Sciences Boris Kidric, Laboratorija za reaktorsku i neutronsku fiziku, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    The objective of the experiment was to measure the axis of the neutron beam from the reactor channel. The collimator, mechanical spectrometer and detectors are to be placed along this axis. Two points along the channel are determined to be defined as centres of the neutron beam. During this experiments the collimators were placed in the reactor at distance of 100 cm and cross section of 3.5 cm in diameter. BF{sub 3} detectors were used for the experiment.

  4. Theoretical analysis of nuclear reactors (Phase I), I-V, Part IV, Nuclear fuel depletion; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, IV Deo, Promena izotopnog sastava goriva

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    Nuclear fuel depletion is analyzed in order to estimate the qualitative and quantitative fuel property changes during irradiation and the influence of changes on the reactivity during long-term reactor operation. The changes of fuel properties are described by changes of neutron absorption and fission cross sections. Part one of this report covers the economic significance of fuel burnup and the review of fuel isotopic changes during depletion. Pat two contains the analysis of the U{sup 235} chain, analytical expressions for the concentrations of U{sup 235}, U{sup 236} and Np{sup 237} as a function of burnup. Part three contains the analysis of neutron spectrum influence on the Westcott method for calculating the cross sections. Part four contains the calculation method applied on Calder Hall type reactor. The results were obtained by applying ZUSE-22 R digital computer.

  5. RB research nuclear reactor - Annual report for 1986, I - III; Istrazivacki nuklearni reaktor RB (Izvestaj o radu u 1986. godini), I-III

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Pesic, M; Vranic, S; Petronijevic, M; Jevremovic, M; Ilic, I [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1987-07-01

    This report includes data concerning the RB reactor operation in 1986, state of the reactor components, data about the employed personnel and the database of experimental and other reactor related devices. It is made of 3 parts: Engineering description and operation of the RB reactor including dosimetry, reactor staff data and financial report; Reactor facility components and maintenance; RB reactor operation and utilization in 1986. Izvestaj pokazuje podatke o radu reaktora RB u toku 1986. godine, stanje reaktorske opreme, podatke o angazovanom osoblju na reaktoru i datoteku sa podacima o eksperimentalnoj i drugoj opremi reaktora RB. Sastoji se od 3 dela: tehnicki opis, pogon i rad reaktora, oprema postrojenja i njeno odrzavanje, koriscenje reaktora u 1986. godini.

  6. II-1 General regulatory guide for staff on duty; II-1 Opsti pravilnik za rad dezurnog osoblja

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    Personnel responsible for RA reactor operation is working in shifts. This regulatory guide describes in detail rights, tasks and responsibilities of each staff member in duty when operating the reactor under regular conditions, during start-up, during shutdown, during repair and maintenance shutdown periods. Rad reaktora odvija se po smenama. Ovaj pravilnik regulise prava, duznosti i odgovornost svakog od clanova tima u smeni pojedinacno u regularnim uslovima rada, prilikom remonta, u toku stajanja, dostizanja nominalne snage, zaustavljanja rada reaktora.

  7. Project RA Research nuclear reactor - Annual report 1993 with comparative review for the period 1991 - 1993; Projekat Istrazivacki nuklearni reaktor RA - Izvestaj za 1993. godinu, uz uporedni pregled za period 1991 - 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-15

    Research reactor RA Annual report for year 1993 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. The ninth separate annex deals with the feasibility of RA reactor applications. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1993. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Poseban prilog razmatra mogucnosti koriscenja istrazivackog reaktora RA. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

  8. Major accident analyses for experimental zero-power fast reactor assemblies; Analyse des accidents graves pouvant survenir dans les reacteurs experimentaux a neutrons rapides de puissance zero; Analiz krupnoj avarii dlya ehksperimental'ny kh reaktornykh ustanovok nulevoj moshchnosti na bystrykh nejtronakh; Analisis de los accidentes graves que pueden producirse en los reactores experimentales rapidos de potencia cero

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, G.; Barts, E. W.; Kapil, S.; Tomabechi, K. [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    autores explican como han adaptado la clave AX-I para calculos neutronico-hidro-dinamicos al caso de un gas que se ajusta a la ecuacion de Van der Waals. Otra modificacion importante introducida en la ecuacion de estado utilizada en la clave, consiste en emplear una ecuacion del tipo de Mie-Gruneisen, derivada de la teoria del estado solido. Esta modificacion permite evaluar de manera mas satisfactoria del termino de presion para el caso de cuerpos de composicion variable. Dado que en un conjunto de potencia cero las placas de uranio fuertemente enriquecido en el isotopo-235, se calentaran con mas rapidez que las de uranio empobrecido, la posibilidad de que se produzca un efecto Doppler positivo neto es mucho mayor en un conjunto experimental que en el reactor de potencia reproductor equivalente. Se ha estudiado este peligro en el caso de diferentes conjuntos posibles. Los calculos indican que en un conjunto de potencia cero el coeficiente Doppler solo alcanza un valor peligroso en los sistemas que poseen un espectro de energias neutronicas muy blando, caracteristico de los grandes reactores de potencia reproductores, alimentados con oxido de uranio. (author) [Russian] Provedeno issledovanie vozmozhnosti, mekhanizma i posledstvij rasplavleniya, a takzhe drugikh krupnykh yadernykh intsidentov dlya ehksperimental'nog o reaktora nulevoj moshchnosti na bystrykh nejtronakh tipa ZPR-III dvukhpolovinchatog o tipa. V dopolnenie k ehtomu issledovaniyu provedena otsenka znacheniya ehffekta Dopplera dlya mnogikh yadernykh reaktornykh ustanovok takogo reaktora. V doklade budet pokazano, chto yavlenie rasplavleniya maloveroyatno vvidu ogranichennogo kolichestva yavlenij, kotorye nuzhno postulirovat'. Posle rassmotreniya mekhanizma razrusheniya budut dany rezul'taty raschetov, svyazannykh s nejtronnoj fizikoj i gidro-dinamikoj , dlya dvukh reaktornykh ustanovok nulevoj moshchnosti. Provedeno issledovanie aktivnoj zony emkost'yu 1200 litrov, kharakternoj dlya otnositel'no bol

  9. Research nuclear reactor RA - Annual Report 1975. Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1975. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    The plan for 1975 was successfully fulfilled. This is reflected in research related to improvement of operating properties of the RA reactor, mostly due to the effort of the RA staff employed in operation and maintenance of the reactor. Fuel saving achieved by this activity amounted to about 38% (80% enriched fuel). Preliminary work is done, concerned with new reactor core with highly enriched fuel. This is a significant saving as well. New fuel elements have arrived at the end of this year. It is going to enable increase of neutron flux by 50% without changing the nominal operating power. The possibility of further improvement of the reactor are analyzed, to enable material testing and production of radioactive sources. Mid term plan for reactor operation was made according to this analysis. It is planned to further increase the neutron flux in isolated smaller zones, and building new experimental loops with cooling and fast neutron converters. Much was done to increase the safety level of reactor operation and preparing the safety report. [Serbo-Croat] Izvrsenje zadataka u 1975. godini bilo je uspesno. To se ogleda u povecanju istrazivackog rada vezanog za poboljsanje eksploatacionih karakteristika reaktora RA, pretezno koriscenjem sopstvenog kadra angazovanog u pogonu i odrzavanju reaktora. Ovim radom postignuta je usteda goriva od oko 38% (80% obogaceno gorivo). Izvrseni su preliminarni radovi na prevodjenju reaktora RA na novo gorivo, sto je takodje velika usteda. Novo gorivo je stiglo krajem godine i ono ce obezbediti porast neutronskog fluksa od 50%, bez promene nominalne snage reaktora. Izvrsena je analiza mogucnosti daljeg usavrsavanja reaktora za potrebe ispitivanja materijala kao i proizvodnju radioaktivnih izvora. Na osnovu ove analize nacinjen je srednjorocni program rada reaktora RA sa tezistem na daljem povecanju fluksa u izdvojenim manjim zonama i ugradnju 'hladjenih petlji' i brzih konvertora. Mnogo je ucinjeno na povecanju stepena sigurnosti

  10. Slow Neutron Spectrometers at the Swedish Reactors; Spectrometres a Neutrons Lents des Reacteurs Suedois; 0421 041f 0415 041a 0422 0420 041e 041c 0415 0422 0420 042b 041c 0415 0414 041b 0415 041d 041d 042b 0425 041d 0415 0419 0422 0420 041e 041d 041e 0412 041d 0410 0428 0412 0415 0414 0421 041a 0418 0425 0420 0415 0410 041a 0422 041e 0420 0410 0425 ; Espectrometros para Neutrones Lentos en los Reactores de Suecia

    Energy Technology Data Exchange (ETDEWEB)

    Dahlborg, U.; Skoeld, K. [AB Atomenergi, Stockholm (Sweden); Larsson, K. -E. [Royal Institute of Technology, Stockholm (Sweden)

    1965-06-15

    uglovogo raspredelenija s ispol'zovaniem kombinirovannogo analiza metodom kristallicheskogo monohromatora i metodom vremeni proleta poluchajut ochen' cennye rezul'taty, nesmotrja dazhe na otnositel'no plohuju intensivnost' i razreshajushhuju sposobnost'. Nedavno byl ispytan mehanicheskij selektor skorostej s razreshajushhej sposobnost'ju 4,2% po dline volny. Odnako jetot pribor poka ne ispol'zuetsja vo vremja jeksperimentov. Spektrometr po vremeni proleta v Studsvike na reaktore R2 moshhnost'ju 30 mgvt s vodnym zamedlitelem ispol'zuetsja v celjah monohromatizacii kombinirovannogo berillie- vogo fjl'tra i preryvatelja s uzkoj krivoj propuskanija. Na jetom spektrometre, a takzhe na spektrometre v Stokgol'me preryvatel' stavitsja pered obrazcom, i tem samym sozdaetsja vozmozhnost' odnovremennoj registracii dannyh pri razlichnyh uglah nabljudenija. Na reaktore R2 takzhe dejstvuet trehosevoj kristallicheskij spektrometr. Privodjatsja razlichnye svojstva raznoobraznyh priborov, naprimer intensivnost', razreshajushhie sposobnosti i prigodnost' dlja opredelennyh izmerenij. Tak, privodjatsja cifry, pokazyvajushhie, chto bol'shaja poterja intensivnosti svjazana s dovol'no ogranichennym uluchsheniem razreshajushhej sposobnosti. Interesno, chto kogda sravnivajutsja mezhdu soboj reaktory R1 i R2 v kachestve nejtronnyh istochnikov dlja raboty s kanalom dlja vypuska puchka, to pri rabote s vyvodom nejtronov potok nejtronov reaktora R2, javljajushhijsja v 100 raz bol'shim, umen'shaetsja primerno v 10 raz. Jeta poterja ob'jasnjaetsja uzkimi kanalami dlja vypuska puchka i fil'trami, neobhodimymi dlja umen'shenija potoka bystryh nejtronov i gamma-izluchenija. Kratko obsuzhdajutsja v celjah illjustracii dannye po rassejaniju H{sub 2}O, poluchennye na razlichnyh priborah. V rezul'tate sravnenija mezhdu soboj reaktora s vodnym zamedlitelem i tjazhelovodnogo reaktora s tochki zrenija raboty kanalov dlja vypuska puchka otchetlivo mozhno videt' preimushhestvo reaktora tjazhelovodnogo tipa. (author)

  11. The use of oxygen-14 in the study of positron polarization in a Fermi-type transition; Emploi de l'oxygene-14 pour l'etude de la polarisation des positions dans une transition du type Fermi; Ispol'zovanie kisloroda-14 dlya issledovaniya polyarizatsii pozitronov v prevrashcheniyakh tipa Fermi; Empleo del oxigeno-14 en el estudio de la polarizacion de los positrones en una transicion de tipo Fermi

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F H; Gerhart, J B; Hopkins, J C; Bichsel, H; Stroth, J [University of Washington, Seattle, WA (United States)

    1962-01-15

    The short-lived radioisotope O{sup 14} has been used in two experiments designed to determine the degree of polarization of the decay positrons. In the two-component theory of beta-decay, first proposed by Lee and Yang, the non-conservation of parity implies that positrons will have their spin angular momentum polarized in the direction of motion by an amount proportional to their velocity divided by the velocity of light. The proportionality constant depends upon the type of interaction responsible for the decay process. The properties of 72-sec O{sup 14} are suitable for a test of certain aspects of the theory. O{sup 14} decays from a zero-spin, even-parity state to another zerospin, even-parity excited state in N{sup 14}. Therefore, the decay is a pure Fermi-type. The O{sup 14} was produced by an N{sup 14} (p, n) O{sup 14} reaction in the University of Washington 60-in cyclotron by a continuous N{sub 2} flow system. O{sub 2} carrier gas was added to the N{sub 2}. After activation the gas passed through suitable filters to remove unwanted activities, and to combine the oxygen with hydrogen. The active water vapour was trapped at liquid N{sub 2} temperature on a copper rod to form a strong ( {approx} 10 mc) continuous source of 72-sec O{sup 14}. Decay positrons were energy-analysed in a small magnetic spectrometer. The longitudinal polarization of the positrons emerging from the spectrometer was studied by two methods. In the first the positrons impinged upon a plastic scintillator where some of them annihilated in flight. The more energetic annihilation quantum is circularly polarized in the same sense as that of the original positron. These gamma rays were Compton-scattered from magnetized iron and detected in a Nal(Tl) scintillation counter. An asymmetry in the scattering crosssection with the direction of magnetization is related to the original amount of positron polarization. In the second method the positrons were focussed upon a magnetized iron foil. The positron-electron, or Bhabha, scattering cross-section depends upon the sense of magnetization of the iron foil relative to the positron polarization. The scattered electron and positron were detected in plastic scintillation-counters operating in fast coincidence. For both methods the expected asymmetries are small, and long counting-periods were required. The results show that 1-MeV O{sup 14} positrons are right-handed polarized. The annihilation method gave the value (0.73 {+-} 0.17) v/c, the Bhabha scattering method gave (0.97 {+-} 0.19) v/c. The simplest theory predicts 1.00 v/c. I t is believed that the Bhabha scattering method is the more reliable, chiefly because the relation between asymmetry and polarization is easier to calculate. (author) [French] Le radioisotope oxygene-14 a courte periode a ete utilise au cours de deux experiences visant a determiner le degre de polarisation des positions de desintegration. Dans la theorie a deux composantes sur la desintegration beta, enoncee pour la premiere fois par Lee et Yang, la non-conservation de la parite implique que l'impulsion angulaire de spin des positions se polarisera dans le sens du mouvement selon une constante proportionnelle a leur vitesse divisee par la vitesse de la lumiere. Cette constante depend du type d'interaction responsable du processus de desintegration. Les proprietes de l'oxygene-14 (periode de 72 s) permettent de verifier experimentalement certains aspects de cette theorie. Lorsqu'un atoms de {sup 14}O se desintegre en {sup 14}N, il passe d'un etat de spin zero, de parite +1, a un autre etat excite, egalement de spin zero et de parite +1. Il s'agit donc d'une desintegration pure du type Fermi. Le {sup 14}O a ete produit par une reaction {sup 14}N (p, n) {sup 14}O realisee dans le cyclotron de 60 pouces de l'Universite de Washington au moyen d'un courant continu de N{sub 2} auquel on a ajoute de l'O{sub 2} comme entraineur. Apres activation, on a fait passer le gaz dans des filtres appropries pour eliminer les activites indesirables et combiner l'oxygene avec de l'hydrogene. La vapeur d'eau active a ete condensee a la temperature de l'azote liquide sur une barre de cuivre, de facon a constituer une source continue d'activite elevee ({approx}10mc) de {sup 14}O (periode de 72 s). L'energie des positons de desintegration a ete analysee dans un petit spectrometre magnetique. La polarisation longitudinale des positons emergeant du spectrometre a ete etudiee de deux facons. Dans le premier cas, les positons frappaient un scintillateur en plastique, et quelques-uns d'entre eux etaient annihiles en cours de vol. Le quantum d'annihilation le plus energique est polarise circulairement dans le meme sens que celui du positon initial. Ces rayons gamma subissaient une diffusion de Compton siu' du fer magnetise et etaient ensuite detectes au moyen d'un compteur a scintillation Nal (T1). L'asymetrie de la section efficace de diffusion par rapport au sens de la magnetisation est fonction de la polarisation initiale des positons. Dans le second cas, on a dirige les positons sur une feuille de fer magnetise. La section efficace de diffusion des positons-electrons (methode de Bhabha) depend alors du sens de la magnetisation de la feuille de fer par rapport a la polarisation des positons. Les electrons et les positons diffuses ont ete detectes au moyen de compteurs a scintillation en plastique, fonctionnant en coincidence rapide. Dans l'un et l'autre cas, les asymetries prevues sont faibles, et des periodes de comptage de longue duree sont necessaires. Les resultats obtenus indiquent que les positons de f MeV emis par le {sup 14}O sont polarises a droite. La methode d'annihilation donne la valeur de (0,73 {+-} 0,17) v/c; la methode de diffusion de Bhabha donne (0.97 {+-} 0,19) v/c. La theorie la plus simple prevoit 1,00 v/c. On pense que la methode de diffusion de Bhabha est la plus sure, car la relation entre l'asymetrie et la polarisation est plus facile a calculer. (author) [Spanish] El radioisotopo {sup 14}O, de periodo de semidesintegracion corto, se ha utilizado en dos experimentos destinados a determinar el grado de polarizacion de los positrones de desintegracion. En la teoria de los dos componentes de la desintegracion beta que enunciaron por primera vez Lee y Yang, la no conservacion de la paridad exige que el impulso angular del spin de los positrones se polarice en el sentido del movimiento en una cantidad proporcional a su velocidad dividida por la de la luz. La constante de proporcionalidad depende del tipo de interaccion al que se deba el proceso de desintegracion. Las propiedades del {sup 14}O de 72 segundos permiten comprobar experimentalmente algunos aspectos de esta teoria. Al desintegrarse en {sup 14}N el {sup 14}O pasa de un estado de spin cero y paridad + 1, a otro estado, excitado, de spin cero y paridad + 1. Por consiguiente, la desintegracion constituye lina transicion de tipo Fermi puro. El {sup 14}O fue obtenido mediante la reaccion {sup 14}N (p, n) O{sup 14} en el ciclotron de 60 pulgadas de la Universidad de Washington, por un sistema de flujo continuo de N{sub 2} al que se agrego O{sub 2} como gas portador. Despues de activado, el gas atraviesa unos filtros para eliminar las actividades indeseadas y para combinar el exigeno con hidrogeno. El vapor de agua activa fue condensado a la temperatura del N{sub 2} liquido sobre una varilla de cobre, para obtener una fuente continua de elevada intensidad (unos 10 mc) de {sup 14}O de 72 segundos. La energia de los positrones de desintegracion fue analizada con ayuda de un pequeno espectrometro magnetico. La polarizacion longitudinal de los positrones a la salida del espectrometro se estudio por dos metodos diferentes. En el primer metodo, los positrones inciden sobre un centelleador de material plastico en el que algunos de ellos son aniquilados en vuelo. El cuanto de aniquilacion, cuya energia es mayor, se polariza circularmente en el mismo sentido que el positron original. Estos rayos gamma son dispersados en hierro imantado por efecto Compton e identificados en un contador de centelleo de Nal(Tl). La asimetria de .la seccion eficaz de dispersion con respecto a la direccion de magnetizacion esta relacionada con la magnitud original de la polarizacion de los positrones. El segundo metodo consistio en dirigir los positrones sobre una lamina de hierro imantada. La seccion eficaz de dispersion positron-electron, o de Bhabha, depende del sentido de la magnetizacion de la lamina de hierro con respecto a la polarizacion de los positrones. Los electrones y positrones dispersos fueron detectados en contadores de centelleo, de material plastico, conectados a un circuito de coincidencias rapidas. En ambos metodos las asimetrias previstas son pequenas, lo cual exige periodos largos de recuento. Los experimentos han demostrado que los positrones de 1 MeV procedentes de {sup 14}O tienen polarizacion dextrogira. El metodo de aniquilacion dio un valor (0,73 {+-} 0,17) v/c; el metodo de dispersion de Bhabha dio (0,97 {+-} 0,19) v/c. La teoria mas simple predice un valor de 1,00 v/c. Se supone que el metodo de dispersion de Bhabha es el que da mejores resultados, sobre todo porque la relacion entre la asimetria y la polarizacion es mas facil de calcular. (author) [Russian] V dvukh ehksperimentakh radioizotop O{sup 14} s korotkim poluperiodom raspada byl vybran dlya opredeleniya stepeni polyarizatsii obrazuyushchikhsya pri raspade pozitronov. V svete teorii dvojnogo betaraspada, predlozhennoj vpervye Li i YAngom, nesokhranenie chetnosti ukazyvaet, chto spinovyj moment kolichestva dvizheniya pozitronov polyariziruetsya v napravlenii dvizheniya na kolichestvo, proportsional'noe ikh skorosti, delennoj na skorost' sveta. Postoyannaya proportsional'nosti zavisit ot roda vzaimodejstviya, vyzyvayushchego protsess raspada. Svojstva 72-sekundnogo O{sup 14} podkhodyat dlya proverki nekotorykh aspektov ehtoj teorii. Kislorod O{sup 14} raspadaetsya ot nulevogo spina, prokhodit cherez chetnoe sostoyanie, perekhodit k drugomu nulevomu spinu i prevrashchaetsya v N{sup 14} v vozbuzhdennom chetnom sostoyanii. Poehtomu raspad proiskhodit tochno po tipu Fermi. Kislorod O{sup 14} byl poluchen reaktsiej N{sup 14} (p, n) O{sup 14} v 60-dyujmovom tsiklotrone Vashingtonskogo universiteta s postoyannym potokom azota N{sub 2}. K N{sub 2} byl dobavlen nositel' O{sub 2} v gazoobraznom vide. Posle aktivizatsii gaz propuskalsya cherez sootvetstvuyushchie fil'try dlya udaleniya nezhelatel'noj aktivnosti i dlya obespecheniya soedineniya kisloroda s vodorodom. Aktivizirovannye vodyanye pary zakhvatyvalis' pri temperature zhidkogo azota N{sub 2} i ulavlivalis' na mednuyu palochku dlya obrazovaniya sil'nogo (okolo 10 millikyuri) postoyannogo istochnika 72-sekundnogo kisloroda O14. Obrazuyushchiesya pri raspade pozitrony analizirovalis' s tochki zreniya ikh ehnergii v nebol'shom magnitnom spektrometre. Dva metoda byli ispol'zovany dlya izucheniya prodol'noj polyarizatsii vykhodyashchikh iz spektrometra pozitronov. V pervom iz nikh pozitrony popadali v plasticheskij stsintillyator, gde nekotorye iz nikh unichtozhalis' na letu. Annigiliruyushchijsya kvant bolee vysokikh ehnergij polyariziruetsya vrashchatel'no v tom zhe samom napravlenii, chto i pervonachal'nye pozitrony. EHti gamma-luchi rasseivalis' iz namagnichennogo zheleza po Komptonu i podschityvalis' pri pomoshchi stsintillyatsionnogo schetchika s Nal(T). Assimetrichnost' poperechnogo secheniya rasseivaniya v zavisimosti ot napravleniya namagnichivaniya svyazana s pervonachal'noj stepen'yu polyarizatsii pozitronov. Vo vtorom metode pozitrony sosredotochenno napravlyalis' na namagnichennuyu zheleznuyu fol'gu. Poperechnoe sechenie rasseivaniya pozitronov-ehlektronov ili rasseivaniya Baba zavisit ot napravleniya namagnichivaniya zheleznoj fol'gi po otnosheniyu k polyarizatsii pozitronov. Rasseyannye ehlektrony i pozitrony obnaruzhivalis' pri pomoshchi plasticheskikh stsintillyatsionnykh schetchikov, rabotayushchikh s bystrym sovpadeniem. Dlya oboikh metodov ozhidaemaya dissimetrichnost' neznachitel'na, i trebuyutsya dlitel'nye promezhutki vremeni podscheta. Rezul'taty pokazyvayut, chto pozitrony O{sup 14} v 1 mehv polyariziruyutsya v napravlenii chasovoj strelki. Metod annigilyatsii daet znacheniya (0,73-0,17) v/c; metod rasseivaniya Baba daet (0,97-0,19) v/c. Prostejshaya teoriya predusmatrivaet 1,00 v/c. Nuzhno dumat', chto metod rasseivaniya Baba bolee nadezhen, glavnym obrazom potomu, chto sootnoshenie mezhdu assimetrichnost'yu i polyarizatsiej bolee legko poddaetsya raschetu. (author)

  12. Research nuclear reactor RA - Annual report 1992; Istrazivacki nuklearni reaktor RA - Izvestaj za 1992. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-12-01

    Research reactor RA Annual report for year 1992 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. Second annex B is a paper by Z. Vukadin 'Recurrence formulas for evaluating expansion series of depletion functions' published in 'Kerntechnik' 56, (1991) No.6 (INIS record no. 23024136. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1992. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Drugi prilog (B) je rad Z. Vukadina 'Recurrence formulas for evaluating expansion series of depletion functions' objavljen u casopisu Kerntechnik, 1991. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

  13. Reproduction of the RA reactor fuel element fabrication; Reprodukcija izrade gorivnog elementa za reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This document includes the following nine reports: Final report on task 08/12 - testing the Ra reactor fuel element; design concept for fabrication of RA reactor fuel element; investigation of the microstructure of the Ra reactor fuel element; Final report on task 08/13 producing binary alloys with Al, Mo, Zr, Nb and B additions; fabrication of U-Al alloy; final report on tasks 08/14 and 08/16; final report on task 08/32 diffusion bond between the fuel and the cladding of the Ra reactor fuel element; Final report on task 08/33, fabrication of the RA reactor fuel element cladding; and final report on task 08/36, diffusion of solid state metals. Ovaj rad sadrzi devet priloga: 1. Zavrsni izvestaj o podzadatku 08/12, ispitivanje elementa goriva reaktora RA; 2. Koncepcija izrade gorivnog elementa reaktora RA; 3. Ispitivanje mikrostrukture gorivnog elementa reaktora RA; 4. Zavrsni izvestaj o podzadatku 08/13, dobijanje binarnih legura urana sa legirajucim komponentama Al, Mo, Zr, Nb i B; 5. Dobijanje legure U-Al; 6. Zavrsni izvestaj o podzadacima 08/14 i 08/16; 7. Zavrsni izvestaj o podzadatku 08/32, difuziona veza goriva i kosuljice gorivnog elementa reaktora RA; 8. Zavrsni izvestaj o podzadatku 08/33, izrada kosuljice gorivnog elementa reaktora RA; 9. Zavrsni izvestaj o podzadatku 08/36, difuzija kod metala u cvrstom stanju.

  14. Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Cupac, S; Vukadin, Z; Stosic, T; Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    This report describes the organisational structure of the technology service and its activities and tasks: routine control of reactor parameters and cooperation with the reactor users; development of methodology of reactor control and its application; control of heavy water and gas system operation; dosimetry measurements of contamination in the reactor building; technical aspects of radiation protection; decontamination and accident analysis. Separate chapter describes building of the reactor experimental loop for irradiation of fuel elements and construction materials, which will be placed in the central experimental channel VK-5. [Serbo-Croat] Ovaj izvestaj opisuje organizacionu semu tehnoloske sluzbe i zadatke koje ona obavlja: rutinska kontrola reaktorsko-fizickih parametara reaktora i saradnja sa korisnicima reaktora, razvojni rad na metodologiji kontrole reaktora i njegovog koriscenja, kontrola rezima rada teskovodnog i gasnog sistema, dozimetrija i tehnicka zastita od zracenja u zgradi reaktora, dekontaminacija i akcidentalna analiza. Posebno poglavlje opisuje izgradnju eksperimentale petlje za ozracivanje gorivnih elemenata i konstrukcionih materijala koja ce biti postavljena u centralnom eksperimentalnom kanalu VK-5 reaktora RA, koja je projektovana kao slozena eksperimentalna instalacija.

  15. Determination of the tritium content in the reactor heavy water, Phase II; Odredjivanje porasta kolicine tritijuma u reaktorskoj teskoj vodi, II faza

    Energy Technology Data Exchange (ETDEWEB)

    Ribnikar, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    Measurement results of the {sup 3}H activity in non-irradiated water and after reactor operation are presented. Methods were developed for sampling and radiochemical water purification by ion exchange and multiple distillation. Methods for absolute measurement of soft beta radiation of tritium were established. Migration of tritium through the heavy water RA reactor system was monitored. Results were compared with other measured reactor parameters. Prikazani su rezultati merenja aktivnosti {sup 3}H u nezracenoj vodi i posle rada reaktora; razradjeni su metodi za uzimanje i radiohemijsko preciscavanje vode putem jonske izmene i visestepene destilacije; postavljeni metodi za apsolutno merenje mekog beta-zracenja tritijuma; pracene su migracije tritijuma kroz teskovodni sistem reaktora; takodje su interpretirani i poredjeni rezultati sa drugim merenim parametrima reaktora.

  16. Decision, Annex 3[Organizational structure of the Division for reactor maintenance]; Prilog br. 3, Odluka

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The objective of the decision about the change in the organizational scheme of the Division for RA reactor maintenance is to achieve efficiency. The tasks are precisely defined as to divide the maintenance and repair tasks from special ones related to improvement of reactor operation its applicability. [Serbo-Croat] U cilju poboljsanja organizacije rada Odelenja odrzavanja reaktora RA, kao i efikasnijeg koriscenja raspolozivog kadra izvrsice se razgranicenje poslova odrzavanja i remonta od posebnih zadataka koji se odnose na poboljsanje rada reaktora i povecanje njegovih mogucnosti.

  17. Action plan for 1965, Annex 2; Prilog br. 2 - Plan zadataka u 1965. godini

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-15

    Action plan presented in this annex includes tasks of the mechanics, electrical and electronic equipment services. It includes a detailed list of planned and preventive maintenance actions related to the heavy water system, technical water system, helium system, reactor core, transportation equipment, hot cells, heating and ventilation systems in the reactor building, power supply system, auxiliary systems in the RA reactor building. [Serbo-Croat] Plan zadataka obuhvata aktivnosti masinske i elektro grupe na preventivnom odrzavanju i planskom remontu sistema teske vode, sistema tehnicke vode, sistema helijuma, centralnog tela reaktora, sistema grejanja i ventilacije, sistema za snabdevanje elektricnom energijom, i ostalih pomocnih sistema u zgradi reaktora RA.

  18. Effect of the plutonium isotopic composition on the performance of fast reactors; Effet de la composition isotopique du plutonium sur le rendement de reacteurs a neutrons rapides; Vliyanie izotopnogo sostava plutoniya na rabotu reaktorov na bystrykh nejtronakh; Efectos de la composicion isotopica del plutonio sobre el funcionamiento de los reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Yiftah, S [Israel Atomic Energy Commission (Israel)

    1962-03-15

    fisionables por neutrones termicos ({sup 239}Pu y {sup 241}Pu), cuanto mas impuro sea el plutonio, tanto menor sera la masa critica y mayor la razon de reproduccion. Tomando como ejemplo el reactor de 1500 l, se comprobo ademas que al eliminar un 40 por ciento del sodio inicialmente presente en el cuerpo, la variacion de reactividad tiende a ser negativa a medida que aumenta la proporcion de isotopos superiores contenidos en el combustible de plutonio (en forma de metal, oxido o carburo). (author) [Russian] Izotopnyj sostav plutoniya, kotoryj dolzhen ispol'zovat'sya v kachestve goryuchego dlya reaktorov na bystrykh nejtronakh, budet zaviset' ot istochnika polucheniya plutoniya. V printsipe vozmozhny tri razlichnykh istochnika: a) proizvodyashchie reaktory; b) teplovye ehnergeticheskie reaktory (ispol'zuyushchie v kachestve topliva estestvennyj ili obogashchennyj uran); c) zony vosproizvodstv a reaktora na bystrykh nejtronakh. V osnovnom istochnik (a) i v nekotorom otnoshenii istochnik (s) budut davat' sravnitel'no 'chistyj' plutonij, t.e. glavnym obrazom plutonij-239, togda kak plutonij iz istochnika (b) budet 'gryaznym', t.e. plutoniem, bogatym izotopami plutoniya-240, plutoniya-241 i plutoniya-242. Stepen' 'zagryazneniya' budet zaviset' ot tipa reaktora, velichiny vygoraniya i voobshche ot istorii oblucheniya topliva. V takom sluchae voznikaet vopros, mozhno li ispol'zovat' v kachestve goryuchego dlya reaktorov na bystrykh nejtronakh lyubye vidy plutoniya. Dlya izucheniya vliyaniya razlichnogo izotopnogo sostava plutonievogo topliva v metallicheskom, oksidnom i karbidnom vide na rabotu reaktorov na bystrykh nejtronakh byli osushchestvleny ogranichennye serii podschetov po 16-gruppovoj diffuzionnoj teorii sfericheskoj geometrii s pomoshch'yu 16-gruppovogo komplekta poperechnykh sechenij, razrabotannogo nedavno Iftakhom, Okrentom i Mol'dauerom s ispol'zovaniem trekh razlichnykh vidov plutoniya, nachinaya s chistogo plutoniya-239 i povyshaya kolichestvo bolee vysokikh izotopov

  19. Design and construction of a fast critical facility; Etude et construction d'un ensemble critique a neutrons rapides; Proektirovanie i sooruzhenie kriticheskoj sborki na bystrykh nejtronakh; Proyecto u construccion de un conjunto critico de neutrones rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Kato, W Y; Dates, L R [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    estudiar las propiedades fisicas de los grandes reactores, altamente diluidos, de com- bustible metalico o ceramico, desprovistos de moderador o parcialmente moderados, con cuerpos de hasta 1500 l de volumen. Los autores describen detalladamente el ZPR-VI y analizan los criterios seguidos en el diseno de sus diversos componentes desde el punto de vista de la fisica de reactores. Asimismo, formulan algunas observaciones acerca de los procedimientos de explotacion y manejo del reactor, los peligros que se pueden presentar durante su funcionamiento, las tecnicas experimentales que conviene emplear y los costos de construccion. (author) [Russian] V programme razrabotki ehnergeticheskikh reaktorov na bystrykh nejtronakh kriticheskaya sborka yavlyaetsya ves'ma poleznym sredstvom dlya kontrolirovani ya vychislitel'nykh metodov, proverki sbornikov sechenij nejtronov i polucheniya vsekh parametrov reaktornoj fiziki, neobkhodimykh dlya proektirovaniya yadernoj ehnergeticheskoj sistemy. 'Poskol'ku ona yavlyaetsya prezhde vsego fizicheskoj sistemoj, proektirovanie kriticheskoj sborki stavit samo po sebe ryad trudnykh problem, ne vstrechayushchikhsya pri proektirovanii ehnergeticheskogo reaktora. Krome obychnykh voprosov, svyazannykh s mestoraspolozheniem , obolochkoj reaktora, raschetom aktivnoj zony i kontrol'no-izmeritel'nym i priborami, voznikayut takie problemy, kak dostizhenie vysokoj stepeni gibkosti, sovmestimoj s bezopasnost'yu, opredelenie razmerov i tipa ustanovki, udovletvoryayushchi kh trebovaniyam ehksperimental'noj fiziki, opredelenie chisla i razmeshcheniya reguliruyushchikh i avarijnykh sterzhnej, svodyashchikh k minimumu posledstviya vozmushchenij, i spetsifikatsiya vosproizvodimost i reguliruyushchikh sterzhnej i drugikh podvizhnykh komponentov s tem, chtoby obespechit' toch- nost', neobkhodimuyu pri izmereniyakh reaktivnosti. EHto lish' nekotorye iz problem, kotorye obsuzhdayutsya v nastoyashchem doklade, osnovannom na poslednem ehksperimente v Argonnskoj natsional

  20. Radioactive Waste Facilities at the Australian Atomic Energy Commission Research Establishment; Installations pour le Traitement des Dechets Radioactifs au Centre de Recherche de la Commission Australienne a l'Energie Atomique; 0423 0421 0422 0414 ; Dispositivos para Evacuacion de Desechos Radiactivos en el Centro de Investigaciones de la Australian Atomic Energy Commission

    Energy Technology Data Exchange (ETDEWEB)

    Berglin, C. L.W.; Keher, L. H.; Miles, G. L.; Wilson, A. R.W. [Australian Atomic Energy Commission Research Establishment, Lucas Heights, Sydney, NSW (Australia)

    1960-07-01

    ha efectuado en las aguas de la zona de las mareas. Se propone enterrar todos los desechos solidos de baja actividad, embalados cuando proceda, y se discuten la eleccion y la situacion de la zona de evacuacion. Se estudia un sistema para almacenar y evacuar desechos solidos de elevada actividad. Se propone la evaporacion y almacenaje de los desechos liquidos de media y baja actividad. Se dan detalles del capital y gastos de funcionamiento de la planta de tratamiento de efluentes y de otros sistemas de manipulacion de desechos. (author) [Russian] V nastojashhem dokumente daetsja opisanie ustanovok, kotorye prednaznachajutsja dlja sbora, obrabotki i udalenija radioaktivnyh othodov v Lukas Hajts v svjazi s predpolagaemym uvelicheniem ob{sup e}ma raboty. Zhidkie othody nizkoj aktivnosti deljatsja na sledujushhie tri vida: stochnye vody, promyshlennye othody iz sistemy ohlazhdenija reaktora, iz tehnicheskih masterskih i drugih otdelenij, v kotoryh otsutstvujut aktivnye veshhestva; jefljuenty iz laboratorij i drugih otdelenij, rabotajushhih s radioaktivnymi materialami. Zavod po obrabotke jefljuentov poslednego tipa glavnym obrazom sostoit iz bakov, v kotoryh proishodit smeshivanie, shhelochnyh bakov, gde osushhestvljaetsja dozirovka, bakov dlja otstoja i ochistki (v kotoryh primenjaetsja process kal'cij-zhelezo-fosfat) i otstojnikov. V dokumente obsuzhdajutsja issleduemye v nastojashhee vremja metody koncentracii otstoja i ego vtorichnoj obrabotki. Obsuzhdajutsja voprosy udalenija othodov i predpolagaemogo ih rastvorenija, poluchennogo na reke Voronora, a takzhe obsuzhdaetsja opyt po rastvoreniju othodov v drugih vodah, gde imejut znachenie priliv i otliv. Esli est' vozmozhnost', to predlagaetsja provodit' zahoronenie vseh othodov v tverdom sostojanii s nizkoj aktivnost'ju, i v dokumente obsuzhdajutsja voprosy vybora mesta takogo zahoronenija. Takzhe obsuzhdajutsja voprosy sozdanija sredstv dlja hranenija i udalenija vysokoaktivnyh othodov v tverdom sostojanii

  1. The Scottish Research Reactor Centre and its Facilities for the Production and Exploitation of Short-Lived Radioisotopes; Le Réacteur de Recherche Ecossais et ses Installations pour la Production et l'Exploitation des Radioisotopes a Courte Periode; ШОТЛАНДСКИЙ ИССЛЕДОВАТЕЛЬСКИЙ РЕАКТОРНЫЙ ЦЕНТР И ЕГО ТЕХНИЧЕСКИЕ СРЕДСТВА ДЛЯ ПРОИЗВОДСТВА И ИСПОЛЬЗОВАНИЯ КОРОТКОЯИВУШХ РАДИОИЗОТОПОВ; El Centro del Reactor de Investigacion de Escocia y sus Instalaciones para la Produccion y Empleo de Radioisotopos de Periodo Corto

    Energy Technology Data Exchange (ETDEWEB)

    Ward, A. [The Royal College of Science and Technology, Glasgow, Scotland (United Kingdom)

    1963-03-15

    , cuartos oscuros, laboratorios para trabajar con actividades del orden del microcurie, criaderos de animales, laboratorios biologicos y quimicos, local de recuento de baja actividad de fondo, sala de conferencias y biblioteca. Se espera que las investigaciones abarquen muchos campos cientificos y tecnologicos. Gran parte de los trabajos se efectuaran con ayuda de radioisotopos de periodo corto. La memoria describe algunos de los proyectos mas caracteristicos. (author) [Russian] V nastojashhee vremja vedetsja stroitel'stvo Shotlandskogo issledovatel'skogo reaktornogo centra, kotoryj vstupit v stroj k vesne 1963 goda. Ustanovka predstavljaet soboj reaktor bakovogo tipa moshhnost'ju 100 kvt s vodjanym ohlazhdeniem i vodografitovym zamedlitelem pri ispol'zovanii obogashhennogo topliva (uran{sup 235}). Jeksperimental'noe tehnicheskoe oborudovanie vkljuchaet bol'shuju teplovuju kolonnu., bol'shoj vodjanoj bak s zashhitoj, a takzhe ustanovku dlja proizvodstva radioizotopov s pnevmaticheskim transporterom. V centre aktivnoj zony imejutsja tri skvoznye truby; imeetsja takzhe odna skvoznaja truba v teplovoj kolonne,a takzhe neskol'ko nebol'shih central'nyh vertikal'nyh stringerov i odin vertikal'nyj stringer secheniem v dkjmov, dohodjashhie do centra aktivnoj zony reaktora. Mnogo gorizontal'nyh stringerov prohodit cherez teplovuju kolonnu, prichem central'nyj stringer prohodit na rasstojanii odnogo dkjma ot toplivnogo baka. V dopolnenie k reaktornomu tehnicheskomu oborudovanie imeetsja mnozhestvo nebol'shih laboratorij. Jeti laboratorii vkljuchajut oborudovanie dlja poluchenija gorjachih istochnikov i raboty s nimi, a takzhe komnatu dlja pereodevanija, jelektricheskie i mehanicheskie masterskie, temnye komnaty, laboratorii dlja raboty s mikrokjurievymi kolichestvami, pomeshhenie dlja zhivotnyh, biologicheskuju i himicheskuju laboratorii, schetnuju komnatu s nizkim urovnem fona, lekcionnyj zal i biblioteku. Predpolagaetsja, chto issledovanija budut kasat'sja mnogih nauchnyh i

  2. The Performance of Major Plant Items at Calder Hall; Fonctionnement des elements principaux de la centrale de Calder Hall; Kharakteristika osnovnykh uzlov ustanovki v Kolder-Kholle; Rendimiento de los principales elementos de la central de Calder Hall

    Energy Technology Data Exchange (ETDEWEB)

    Desbruslais, E. L. [United Kingdom Atomic Energy Authority, Seascale, Cumberland (United Kingdom)

    1963-10-15

    elementos mas importantes de la central contra danos accidentales que puedan provenir de fuentes externas. Para el generador diesel de emergencia, no parece necesario prever un arranque automatico o circuitos paralelos, si bien una centralizacion no seria superflua. (author) [Russian] V techenie svyshe shesti let bol'shaya ustanovka v Kolder-Kholle ehkspluatiruetsya kak ehnergeticheskaya ustanovka s bazovoj nagruzkoj. Na nej voznikali takie khe povrezhdeniya, kak i na obychnykh ehnergeticheskikh ustanovkakh. Vse povrezhdeniya imeli mesto v obychnoj ustanovke i ni odnogo - v samikh yadernykh reaktorakh. Opyt pokazal, chto s tochki zreniya bezopasnosti reaktory i osnovnye uzly ustanovki vmeste s privodami sistemy neobkhodimo rassmatrivat' v tselom. Ne obnaruzheno nikakikh sushchestvennykh izmenenij, kotorye by davali povod dumat' o tom, chto korpus vysokogo davleniya reaktora ili grafitovyy zamedlitel' ogranichat srok ehkspluatatsii ustanovki. Asimmetrichnoe raspredelenie temperatury imeet mesto vokrug vykhodnykh gazovykh truboprovodov, i v nastoyashchee vremya ehto ogranichivaet moshchnost' reaktora. Rekomenduetsya ustanovit' vnachale dopolnitel'noe kolichestvo termopar, kontrol'no-izmeritel'nye pribory dlya opredeleniya napryazheniya i obespechit' vizual'noe nablyudenie za oblastyami vysokogo napryazheniya i temperatury. V khode normal'noj ehkspluatatsii osushiteli bol'she ne primenyayutsya, i sootvetstvenno v rezul'tate ehtogo dostignuto nebol'shoe uvelichenie moshchnosti reaktora. Dastsya rekomendatsii otnositel'no periodichnosti obsledovanij teploobmennikov, osnovnykh gazovykh truboprovodov i nizhnikh uzlov. Nebol'shoe uvelichenie v proizvodstve para dostignuto v rezul'tate umen'sheniya perepuska gaza. Nebol'shie trudnosti voznikli lish' pri ehkspluatatsii tsirkulyatorov gaza tsentrobezhnogo tipa. Otmecheno nebol'shoe snizhenie proizvodstva vnachale v rezul'tate krugovogo iskreniya kommutatorov pri vysokom napryazhenii na motorakh ventilyatorov i na generatorakh

  3. Radiation protection at the RA Reactor in 1985, Part -2, Annex 2c, Reconstruction of the measuring device on the meteorology tower; Deo 2 - Zastita od zracenja kod reaktora RA u 1985. godini - Prilog 2c - Rekonstrukcija merne instalacije na meteoroloskom stubu

    Energy Technology Data Exchange (ETDEWEB)

    Savic, Z; Stevanovic, M; Kovacevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-12-01

    Original meteorology measuring instrumentation dates from 1960-1961. In order to enable more efficient measurements it was indispensable to reconstruct measuring devices completely. Description of the reconstruction works and specification is included in this report. [Serbo-Croat] Prvobitna instrumentacija namenjena meteoroloskim merenjima datira iz perioda 1960-1961. Sa ciljem da se merenja usavrse bilo je neophodno rekonstruisati celokupnu mernu opremu. Opis rekonstrukcije i specifikacija opreme sadrzani su u ovom izvestaju.

  4. Theoretical analysis of nuclear reactors (Phase III), I-V, Part V, Establishment of Monte Carlo method for solving the integral transport equation; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-V, V Deo, Postavljanje Monte Carlo metode za resavanje integralnog oblika transportne jednacine

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    General mathematical Monte Carlo approach is described with the elements which enable solution of specific problems (verification was done by estimation of a simple integral). Special attention was devoted to systematic presentation which demanded explanation of fundamental topics of statistics and probability. This demands a procedure for modelling the stochastic process i.e. Monte Carlo method. Dat je matematicki prilaz Monte Carlo metodi uopste, a po elementima koji dozvoljavaju konkretno resavanje izvesnih problema. (Provera je izvrsena na estimiranju prostog integrala). Narocito je vodjeno racuna o sistematicnosti izlaganja materije sto je mestimicno zahtevalo tretiranje i osnovnih pojmova, statistike i verovatnoce, a sve to skupa zahteva postupak modeliranja stohastickog procesa odnosno Monte Carlo metod (author)

  5. Irradiated uranium reprocessing, Final report I-VI, IV Deo IV - Separation of uranium, plutonium and fission products from the irradiated fuel of the reactor in Vinca; Prerada ozracenog urana. Zavrsni izvestaj - I-VI, IV Deo - Odvajanje urana, plutonijuma i fisionih produkata iz isluzenog goriva reaktora u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za visoku aktivnost, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This study describes the technology for separation of uranium, plutonium and fission products from the radioactive water solution which is obtained by dissolving the spent uranium fuel from the reactor in Vinca. The procedure should be completed in a hot cell, with the maximum permitted activity of 10 Ci.

  6. Conclusions of the experts group of the RA reactor at the meeting held on November 2 and 3 1964 - Annex 12a; Prilog 12a - Zakljucci sa sastanka Strucnog kolegijuma reaktora RA odrzanog na dan 2. i 3. novembra 1964. godine

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    Conclusions of the experts group of the RA reactor are related to: analyses of reactor operation at 6.5 MW power with heavy water coolant flow of 250 m{sup 3}/h (2 pumps rotation speed 1500 rotations/min); decisions of future operation; further preparation activities related to reactor operation in forced regime and reduced cooling conditions.

  7. Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia; Dvadeset godina hemije vezane za potrebe i koriscenje nuklearnih reaktora u Institutu za nuklearne nauke 'Boris kidric' i Vinci - Radiohemija

    Energy Technology Data Exchange (ETDEWEB)

    Dizdar, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    The history of the work in the field of radiochemistry at the Boris Kidric Institute of nuclear sciences, Vinca, Yugoslavia, is given. The technical, organization and staff conditions on which further successful development in this domain depends are discussed (author) [Serbo-Croat] Daje se istorijat rada na radiohemiji u Institutu za nuklearne nauke 'Boris Kidric' u Vinci od njegovog osnivanja do danas. Govori se o tehnickim, organizacionim i kadrovskim uslovima od kojih zavisi dalji uspesan razvoj ove oblasti (author)

  8. Actions needed for RA reactor exploitation - I-IV, Part I, Thermotechnical experiments related to RA reactor hot start-up; Radovi za potrebe eksploatacije reaktora RA - I-IV, I Deo, Termotehnicki eksperimenti u vezi pustanja rektora RA na snagu

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Heavy water coolant loop of the RA reactor includes the reactor, circulation pumps, heat exchangers and pipes. The objective of this task was measuring the thermal parameters of the RA reactor during operation. This report contains the results of the experiment, calculations of thermal regime for the outer and inner tubes, maximum temperature of the fuel element, fluid flow rate in the reactor channels, temperature of the coolant and fuel element cladding.

  9. Action plan for the task: Physical measurements at the RA reactor related to VISA-2 project, '0' program, Reactor start-up and measurement of basic parameters of the new core; Plan rada po zadatku: Fizicka merenja na reaktoru RA u vezi projekta VISA-2, '0' program, Pustanje u rad reaktora RA i merenje osnovnih parametara novog jezgra

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-01

    This report consists of two parts. Part one describes the RA reactor start-up, measurements of thermal neutron flux distribution, measurements of epithermal flux, fast neutron flux distribution, absolute values of both thermal and fast neutron fluxes, calibration of regulating rods, and measurements of neutron flux inside the fuel elements. All the mentioned measurements were done at low power level. Part two includes description of the reactor power increase up to nominal value of 6.5 MW, and measurements of thermal neutron flux distribution under xenon poisoning conditions, measurements of epithermal neutrons, absolute values of both thermal and fast neutron fluxes, and measurements of thermal and epithermal neutron fluxes at the exit of the horizontal experimental channel HK-d.

  10. Radioactivity in the environment of the RA nuclear reactor in Vinca for the period 1977-1980. Material prepared for the RA reactor safety report; Radioaktivnost okoline nuklearnog reaktora RA u Vinci u periodu 1977-1980, Materijal pripremljen za izradu Sigurnosnog izvestaja za reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    Ajdacic, N; Martinc, R [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1980-12-15

    Review of the environmental monitoring data presented in this report is prepared for the RA reactor safety report. These data resulted from four-year monitoring of precipitations and deposited dust. Measurements were done daily. In addition to these data, tables contain mean daily values, total monthly values of beta activities of precipitation from 1977 - 1980. Radioactivity control of the RA reactor environment showed that there was no significant discrepancy compared to the mean values for several years, apart from seasonal variations and meteorological influences. In the period from October 1976 to mid 1978 a number of higher values were recorded probably due to nuclear explosions. During 1979 the general activity level was relatively low, showing increase tendency during 1980.

  11. RA Reactor operation and maintenance (I-IX), part V, Task 3.08/04-06, Refurbishment of the heavy water pumps; Pogon i odrzavanje reaktora RA (I-IX), V Deo, Zadatak 3.08/04-06 Remont teskovodnih pumpi

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Nikolic, M; Milic, J [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    In addition to detailed instructions for maintenance and repair of the heavy water pumps at the RA reactor this document includes nine annexes. They are as follows: cleaning the heavy water pump Avala with distilled water; instructions for repair of the pump CEN-132 (two annexes); list of operating characteristics of the pumps before repair; conclusions of the experts concerning the worn out bearings of the heavy water pump Avala, with the analysis of the stellite layer; report on the completed repair actions on the pumps Avala and CEN-132; report on the measurements done on the pump Avala; and the certificate concerning inspection of the pump.

  12. Theoretical analysis of nuclear reactors (Phase III), I-V, Part IV, Influence of isotopic composition of nuclear fuel on the reactivity with constant flux; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-IV, IV Deo, Uticaj promene izotopnog sastava goriva na reaktivnost uz konstantan fluks

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    Part one of this report presents a series of differential equations describing the nuclear fuel depletion during reactor operation. This series of differential equations is extended to describe the fission products. This part includes equations for effective multiplication factor k{sub eff} and reactivity {rho} as a function of irradiation {tau}. Part two includes results obtained on the analog computer PACE 231 R, and related to Calder Hall type reactor. Part three covers detailed preparation of the series of equations for solution by using the analog computer. Part four includes the list of references related to this task.

  13. Dispersions of Oxides in Oxide Matrices as High-Temperature Reactor Fuels; Dispersions d'oxyde dans des matrices d'oxyde, utilisees comme combustibles dans des reacteurs a haute temperature; Dispersiya okisej v okislovykh matritsakh v kachestve topliva dlya vysokotemperaturnogo reaktora; Empleo de dispersiones de oxidos en matrices de oxidos, como combustibles para reactores de elevada temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Williams, J. [Atomic Energy Research Establishment, Harwell (United Kingdom)

    1963-11-15

    The potential usefulness of dispersions of PuO{sub 2}, UO{sub 2} and ThO{sub 2} in matrices of BeO, Al{sub 2}O{sub 3}, MgO and SiO{sub 2} is reviewed in terms of fuel integrity and fabrication. Dimensional stability and fission-product retentivity are the two features most important to fuel integrity. Compatibility of the constituents of the fuels with one another and with the coolant will influence dimensional stability, but oxide fuels are well favoured in these respects. Dimensional changes under irradiation will contain contributions from neutron and fission fragment damage to the matrix, from radiation damage to the fissile-fertile phase and from agglomerated fission-product gases. Thermal stresses are also capable of effecting changes in shape. However, information on mechanisms for stress relaxation is too limited to enable any reasonable theoretical assessment of behaviour to be made. Both light irradiation and high burn-up studies of fission-product release from the fissile-fertile oxides have concerned themselves mainly with the gaseous products, chiefly xenon. Data on the release of other fission products is very limited as is also information on the movement of fission products in general through the potential matrix materials. Studies of the permeability of sintered pure oxides indicate that densities of at least 95% theoretical density (maybe even 98%) will be needed to eliminate open porosity in such matrices. A variety of techniques are available for the preparation of fissile-fertile particles, for their coating and for their incorporation into high-density matrices. Work on laboratory-scale fabrication processes is well advanced. (author) [French] L'auteur examine la possibilite d'utiliser des combustibles disperses - PuO{sub 2}, UO{sub 2} et ThO{sub 2} et matrices de BeO, Al{sub 2}O{sub 3}, MgO et SiO{sub 2} - dans des reacteurs a haute temperature, au point de vue de l'integrite du combustible et de sa transformation. La stabilite dimensionnelle et l'aptitude a retenir les produits de fission sont les deux caracteristiques les plus importantes de l'integrite du combustible. La compatibilite des elements constitutifs des combustibles les uns avec les autres et avec le refroidisseur exerce une influence sur la stabilite dimensionnelle, mais les combustibles sous forme d'oxydes presentent beaucoup d'avantages a cet egard. Les variations de dimension sous irradiation ont trois composantes: les dommages causes a la matrice par les neutrons et les produits de fission, les dommages causes par les rayonnements a la phase produit fissile/produit fertile, les effets d'une accumulation de produits de fission gazeux. Les contraintes thermiques peuvent egalement etre a l'origine de modifications de forme. Cependant, les renseignements dont on dispose sur les mecanismes de la relaxation des contraintes sont trop limites pour qu'il soit possible de formuler des appreciations theoriques sur le comportement du materiau. Les etudes sur le degagement des produits de fission provenant d'un melange d'oxydes fissiles et fertiles sous faible irradiation ou pour un taux de combustion eleve, ont porte principalement sur les produits gazeux, notamment le xenon. Les donnees sur le degagement d'autres produits de fission sont tres limitees comme le sont d'ailleurs celles qui ont trait aux mouvements des produits de fission en general a travers les materiaux que l'on peut utiliser pour les matrices. Des etudes relatives a l'etancheite des oxydes purs frittes indiquent qu'il faut atteindre des densites egales a 95% au moins et peut-etre meme a 98% de la densite theorique pour supprimer la porosite ouverte dans de telles matrices. On peut recourir a diverses methodes pour preparer des particules de produits fissiles et fertiles, pour les revetir et pour les incorporer dans des matrices de densite elevee. Les travaux sur les procedes de transformation a l'echelle du laboratoire sont assez avances. (author) [Spanish] El autor examina la posibilidad de utilizar dispersiones de PuO{sub 2}, UO2 y ThO{sub 2} en matrices de BeO, Al{sub 2}O{sub 3}, MgO y SIO{sub 2}, desde el punto de vista de la integridad y elaboracion del combustible. Las dos caracteristicas mas importantes en lo que atane a la integridad del combustible son su estabilidad dimensional y su capacidad de retener los productos de fision. La compatibilidad de los componentes del combustible entre si, y entre ellos y el refrigerante, influye en la estabilidad dimensional, pero en este aspecto, las propiedades de los combustibles en forma de oxido son satisfactorias. A la alteracion de las dimensiones del combustible por irradiacion contribuyen los factores siguientes: deterioracion de la matriz por los neutrones y los fragmentos de fision, deteriorizacion de la fase fisionable/fertil por las radiaciones y gases de los productos de fision acumulados. Las tensiones termicas pueden tambien provocar deformaciones. Los conocimientos que se poseen sobre los mecanismos de atenuacion de tensiones son, sin embargo, insuficientes para permitir un estudio teorico razonable del comportamiento de los materiales. Los estudios sobre la liberacion de productos de fision por los oxidos fisionables/fertiles, realizados tanto en condiciones de irradiacion poco intensa como de elevado grado de combustion, han tratado principalmente de los productos gaseosos, en particular del xenon. Los datos que se poseen sobre el desprendimiento de otros productos de fision son muy escasos, lo mismo que los conocimientos sobre el movimiento de los productos de fision en general a traves de los materiales que podrian utilizarse como matrices. De los estudios realizados sobre la permeabilidad de los oxidos puros sinterizados, se deduce que se deberan alcanzar densidades teoricas de 95%, como minimo, o quiza incluso de 98%, paca eliminar la porosidad de dichas matrices. Se han elaborado una serie de procedimientos para preparar las particulas fisionables/fertiles, para revestirlas y para incorporarlas en matrices de elevada densidad. Los trabajos sobre metodos de elaboracion en escala experimental se hallan bastante avanzados. (author) [Russian] Daetsya obzor vozmozhnosti primeneniya dispersij PuO{sub 2},UO{sub 2}, ThO{sub 2} v matritsakh iz BeO, Al{sub 2}O{sub 3}, MgO i SiO{sub 2} s tochki zreniya sokhraneniya tselostnosti takogo topliva i sposobov ego izgotovleniya. Neizmennost' razmerov i sposobnost' uderzhaniya produktov deleniya yavlyayutsya naibolee vazhnymi svojstvami s tochki zreniya sokhraneniya tselostnosti topliva. Sovmestimost' sostavnykh ehlementov topliva drug s drugom i s teplonositelem okazyvayut vliyanie na neizmennost' razmerov, no v ehtom otnoshenii okislovye vidy topliva obladayut znachitel'nymi preimushchestvami. Na izmenenie razmerov pod dejstviem oblucheniya okazyvayut vliyanie: povrezhdeniya matritsy pod dejstviem nejtronov i oskolkov deleniya; radiatsionnoe povrezhdenie fazy delyashchikhsya veshchestv vosproizvodyashchikh materialov i nakoplenie produktov deleniya v gazoobraznom sostoyanii. Termicheskie napryazheniya takzhe mogut vyzyvat' izmeneniya formy. Odnako svedeniya o mekhanizme relaksatsii napryazhenij slishkom ogranicheny, chtoby mozhno bylo dat' kakuyu-libo priemlimuyu teoreticheskuyu otsenku povedeniyu topliva. Issledovaniya vykhoda produktov deleniya kak v sluchae legkogo oblucheniya, tak i pri sil'nom vygoranii okisej delyashchikhsya veshchestv/vosproizvodyashchikh materialov ogranichivalis' glavnym obrazom gazoobraznymi produktami deleniya, preimushchestvenno ksenonom. Dannye o vykhode drugikh produktov deleniya, a takzhe svedeniya o prokhozhdenii produktov deleniya voobshche cherez vozmozhnye materialy dlya matrits ochen' ogranicheny. Issledovaniya pronitsaemosti chistykh spekshikhsya okisej pokazyvayut, chto dlya ustraneniya otkrytoj poristosti takikh matrits potrebovalos' by dostizhenie plotnostej, dokhodyashchikh po men'shej mere do 95, a to i do 98% ot teoreticheski osushchestvimoj. Dlya izgotovleniya chastits delyashchikhsya veshchestv/vosproizvodyashchikh materialov, dlya ikh pokrytiya i dlya ikh vklyucheniya v matritsy bol'shoj plotnosti imeetsya bol'shoe raznoobrazie metodov. Rabota po vyrabotke tekhnologicheskikh protsessov izgotovleniya v laboratornom masshtabe uzhe dostatochno podvinulas'. (author)

  14. Physical measurements at the RA reactor related to VISA-2, e. Measurements of flux and reactivity during RA reactor operation and exploitation; Fizicka merenja na reaktoru RA u vezi projekta VISA-2, e. Pracenje fluksa i reaktivnosti u toku eksploatacije reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-05-15

    This report includes the following: characteristics of neutron flux in vertical experimental channels of the RA reactor; characteristics of neutron flux in VISA-2 channels; reactivity changes in the reactor during VISA-2 irradiation including calibration of control rods.

  15. Accident conditions analysis of spent fuel storage pool RA research reactor in Vinca; Analiza udesnih stanja u odlagalistu isluzenog goriva istrazivackog rektora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Jovic, V; Jovic, L [Institute of Nuclear Sciences VINCA, Belgrade (Serbia and Montenegro)

    2000-07-01

    Based on Safety analysis of the spent fuel pool RA research reactor in Vinca, conditions and possibilities accident sequences in present configuration storage facility are considered (author) [Serbo-Croat] Na osnovu Analize sigurnosti odlagalista isluzenog goriva istrazivackog reaktora RA u Vinci razmatraju se uslovi i mogucnosti pojave udesnih stanja u postojecoj konfiguraciji odlagalista (author)

  16. RA research nuclear reactor - Annual report 1985; Istrazivacki nuklearni reaktor RA - Izvestaj za 1985. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1985 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  17. RA Research reactor, Annual report 1986; Istrazivacki nuklearni reaktor RA - Izvestaj za 1986. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1986 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  18. Annual report of the maintenance division for 1965; Godisnji izvestaj Odelenja odrzavanja za 1965. g

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The personnel of the Division is organized in groups, each responsible for a number of tasks related to maintenance of reactor mechanical structures, electric equipment, electronic equipment. According to the action plan for 1965 the division for RA reactor maintenance the main activities were: planned maintenance of the reactor components, planned repair of the main components, indispensable repairs during reactor operation, repair during planned shutdown periods and tasks related to improvement of operation components and systems. Quite a significant number of failures was related to electronic equipment resulting from failures of thermometers in the heavy water system due to vibrations of the pumps. A number of spare parts and tools were produced needed for maintenance of reactor components, as well as instruments for control and calibration of reactor measuring devices. [Serbo-Croat] Odelenje odrzavanja reaktora RA organizovano je po grupama, od kojih je svaka odgovorna za odrzavanje pojedinih delova sistema: masinske opreme, elektricne opreme, elektronskih uredjaja. Prema planu rada za 1965. godinu Odelenja za odrzavanje reaktora RA osnovne aktivnosti bile su: planirano odrzavanje komponenti reaktora, planirane popravke osnovnih komponenti, neodlozne popravke tokom eksploatacije i u toku planiranih zaustavljanja kao i usavrsavanje opreme i sistema. Znatan broj kvarova pojavio se na elektronskoj opremi usled kvarova termometara u sistemu teske vode usled vibracija koje izazivaju pumpe. Odredjeni broj delova izradjen je za potrebe odrzavanja komponenti reaktora, kao i instrumenata za kontrolu i kalibraciju mernih uredjaja.

  19. High-Temperature Gas-Cooled Reactor Critical Experiment and its Application to Thorium Absorption Rates; Experience Critique pour l'Etude d'un Reacteur a Haute Temperature, Refroidi par un Gaz et son Application a la Determination des Taux d'Absorption du Thorium; Kriticheskij opyt, postavlennyj na vysokotemperaturnom reaktore s gazovym okhlazhdeniem, i primenenie ego dlya opredeleniya stepeni pogloshcheniya toriya; Experimento Critico Efectuado en un Reactor de Elevada Temperatura Refrigerado por Gas y su Aplicacion para Calcular los Indices de Absorcion del Torio

    Energy Technology Data Exchange (ETDEWEB)

    Bardes, R. G.; Brown, J. R.; Drake, M. K.; Fischer, P. U.; Pound, D. C.; Sampson, J. B.; Stewart, H. B. [General Dynamics Corporation,San Diego, CA (United States)

    1964-04-15

    significativo debido a que en las obras publicadas subsiste cierta divergencia en los resultados obtenidos con ambas tecnicas. (author) [Russian] Pri razrabotke idei reaktora HTGR i ego pervogo prototipa v Pich- Bottome prishli k resheniju o neobhodimosti obespechit' sootvetstvujushhie ishodnye dannye dlja provedenija jadernogo analiza. Konkretnye potrebnosti teorii jadernogo proektirovanija na ishodnyh dannyh otnositel'no pogloshhenija torija priveli k sozdaniju jeksperimental'nogo proekta, sostojashhego iz kriticheskoj sborki tipa sborki s central'noj reshetkoj s okruzhajushhim ammortizatorom i peredvizhnymi aktivnymi zonami. Sborka takogo tipa, v kotoroj v sravnitel'no nebol'shoj central'noj reshetke s zhelaemoj geometriej mozhet byt' ustanovlen predstavljajushhij interes spektr, javljaetsja poleznoj ustanovkoj dlja poluchenija raznoobraznyh ishodnyh dannyh v celjah provedenija jadernogo analiza novyh idej. Obsuzhdajutsja konkretnye preimushhestva jetogo metoda po sravneniju so stroitel'stvom sborki-modeli, a takzhe rol' teorii v opredelenii, kakie opyty javljajutsja naibolee poleznymi i kak jeti opyty zatem ispol'zujutsja pri proverke metodov proektirovanija. - Byli razrabotany dva sravnitel'no novyh metoda dlja ispol'zovanija v sborke reshetok - metod izmerenija kolebanij reaktivnosti dlja opredelenija kojefficienta Dopplera dlja torija i metod aktivacii dlja opredelenija kak rezonansnogo integrala torija, dispergirovannogo v grafite, tak i ego zavisimosti ot temperatury (kojefficient aktivacii Dopplera). Pri izmerenii kojefficienta Dopplera putem opredelenija kolebanij reaktivnosti ves' central'nyj toplivnyj jelement ispol'zovalsja takim obrazom, chto byla vozmozhnost' osushhestvit' nagrev toplivnogo jelementa do 800 Registered-Sign F i tochno opredelit' opytnym putem teplovye jeffekty, t.e. te jeffekty, kotorye ne okazyvajut vlijanija na velichinu rezonansvogo zahvata torija. Sravnenie rezul'tatov s teoriej dlja rjada uslovij svidetel'stvuet o prekrasnom soglasovanii

  20. Congenital Primary Pachydermoperiostosis and Striate Palmoplantar Keratoderma - a Case Report

    OpenAIRE

    Stojanović Slobodan; Vučković Nada; Jovanović Marina; Petrović Kosta

    2014-01-01

    Uvod. Pahidermoperiostoza (PDP) predstavlja heterogeni sindrom za koji su karakteristične hipertrofi čne promene prvenstveno kože i kostiju ekstremiteta: pahidermija, klabing (clubbing) prstiju šaka i stopala i hipertrofi čna osteoartropatija. Primarna pahidermoperiostoza − sinonim Turen−Solent−Goleov sindrom (Touraine-Solente-Golé) (PPDP), ili primarna hipertrofi čna osteoartropatija (PHO), redak je nasledni poremećaj i predstavlja jedan od dva tipa hipertrofi čne osteoartropatije....

  1. Evaluation of glyphosate resistance in Arabidopsis thaliana expressing an altered target site EPSPS.

    Science.gov (United States)

    Sammons, R Douglas; You, Jinsong; Qi, Youlin; Flasinski, Stanislaw; Kavanaugh, Christina; Washam, Jeannie; Ostrander, Elizabeth; Wang, Dafu; Heck, Greg

    2018-05-01

    Glyphosate-resistant goosegrass has recently evolved and is homozygous for the double mutant of EPSPS (T 102 I, P 106 S or TIPS). These same mutations combined with EPSPS overexpression, have been used to create transgenic glyphosate-resistant crops. Arabidopsis thaliana (Wt EPSPS K i ∼ 0.5 μM) was engineered to express a variant AtEPSPS-T 102 I, P 106 A (TIPA K i = 150 μM) to determine the resistance magnitude for a more potent variant EPSPS that might evolve in weeds. Transgenic A. thaliana plants, homozygous for one, two or four copies of AtEPSPS-TIPA, had resistance (IC 50 values, R/S) as measured by seed production ranging from 4.3- to 16-fold. Plants treated in reproductive stage were male sterile with a range of R/S from 10.1- to 40.6-fold. A significant hormesis (∼ 63% gain in fresh weight) was observed for all genotypes when treated at the initiation of reproductive stage with 0.013 kg ha -1 . AtEPSPS-TIPA enzyme activity was proportional to copy number and correlated with resistance magnitude. A. thaliana, as a model weed expressing one copy of AtEPSPS-TIPA (300-fold more resistant), had only 4.3-fold resistance to glyphosate for seed production. Resistance behaved as a single dominant allele. Vegetative tissue resistance was 4.7-fold greater than reproductive tissue resistance and was linear with gene copy number. © 2017 The Authors. Pest Management Science published by John Wiley & Sons Ltd on behalf of Society of Chemical Industry. © 2017 The Authors. Pest Management Science published by John Wiley & Sons Ltd on behalf of Society of Chemical Industry.

  2. Study of Fluidized-Bed Control Rods; Etude de Barres de Controle Fluidisees; Izuchenie reguliruyushchej sistemy, ispol'zuyushchej suspenziyu pogloshchayushchikh chastits; Estudio Sobre Barras de Control de Lecho Fluidificado

    Energy Technology Data Exchange (ETDEWEB)

    Blair, D. J. [General Nuclear Engineering Corporation, Dunedin, FL (United States); Driscoll, M. J.; Dalton, G. R.; Parkinson, T. F. [Department of Nuclear Engineering, University of Florida, Gainesville, FL (United States)

    1964-06-15

    sistemu trub podobno sistemam upravlenija, razrabatyvaemym dlja reaktorov s suspenziej topliva. Nekotorye iz vozmozhnyh preimushhestv koncepcii SPCh: 1) ustranjaetsja bol'shinstvo vvodov v verhnjuju chast' korpusa i uproshhaetsja process peregruzki topliva; 2) pri vozniknovenij avarii v rezul'tate poteri potoka proishodit avtomaticheskaja bystraja ostanovka reaktora; 3) osevoe raspredelenie moshhnosti mozhet izmenjat'sja v rezul'tate primenenija special'nyh kanalov ili chastic peremennoj velichiny; 4) rezkoe vozrastanie potoka v vodjanom zazore mozhet byt' umen'sheno dlja chastichno izvlechennogo upravljajushhego sterzhnja; 5) mozhno umen'shit' temperaturnyj ''zapas'' reaktivnosti,esli sistema imeet otricatel'nyj temperaturnyj kojefficient; 6) rashody po izgotovleniju znachitel'no nizhe, chem dlja jelektromehanicheskih sistem. Provedena ocenka koncepcii SMCh, v tom chisle bylo osushhestvleno stroitel'stvo pro- totipnyh modelej i proverka gidravlicheskih i jadernyh harakteristik. Izuchalis' dva tipa: propuskajushhie ''sterzhni'' (tolshhina 2 srednih svbbodnyh probega) i otrazhajushhie ''sterzhni'' (tolshhina 4 srednih svobodnyh probega). Dlja oboih tipov mozhno poluchit' priemlimye gidravlicheskie i jadernye harakteristiki. Obosnovana vozmozhnost' upravlenija reaktorami nizkoj moshhnosti s pomoshh'ju propuskajushhih ili otrazhajushhih upravljajushhih ' sterzhnej''. Dalee bylo pokazano, chto SPCh obladajut horoshimi regulirujushhimi svojstvami, kotorye mozhno rasschitat' standartnymi metodami. V sluchae bol'shoj moshhnosti i vysokoj temperatury neobhodima dopolnitel'naja informacija otnositel'no harakteristik materiala chastic. Bol'shoe preimushhestvo SPCh zakljuchaetsja v vozmozhnosti formirovanija osevogo potoka libo putem ispol'zovanija chastic razlichnoj velichiny i pogloshhenija, libo zhe putem.sootvetstvujushhego formirovanija oblasti poperechnogo sechenija SPCh. (author)

  3. A Rapid-Insertion Control-Absorber Mechanism for Use in Hollow Fuel Elements; Mecanisme d'Insertion Rapide d'Absorbants pour Utilisation dans des Elements Creux; Mekhanizm bystrogo vvoda poglotitelya dlya ispol'zovaniya v polykh toplivnykh ehlementakh; Mecanismo para la Insercion Rapida de Absorbentes en Elementos Combustibles Huecos

    Energy Technology Data Exchange (ETDEWEB)

    King, E. S.F. [Atomic Energy Research Establishment Harwell, Berks. (United Kingdom)

    1964-06-15

    alrededor del absorbente es grande, de modo que este ultimo cae libremente cuando se suelta, venciendo solamente la resistencia debida a la viscosidad del moderador refrigerante, siendo detenido por un tope situado en una barra central que corre a lo largo del tomillo-guia hasta un amortiguador de muelle anular situado en la parte superior del mecanismo. Despues de soltar el absorbente, el obturador es desplazado hacia abajo por el motor, a toda velocidad, para volver a enganchar el absorbente. El dispositivo cabe en el elemento combustible y puede ser extraido del reactor junto con dicho elemento o separadamente, por medio de la caja de descarga de combustible. (author) [Russian] V nastojashhem doklade opisyvaetsja tehnicheskij proekt i harakteristika mehanizma s bystro vvodimym poglotitelem dlja ispol'zovanija vnutri polyh vertikal'nyh Toplivnyh jelementov reaktorov, prednaznachennyh dlja ispytanija materialov, tipa DIDO s potokom teplovyh nejtronov 10{sup 14} n/cm{sup 2}/sek. Pervonachal'noe uskorenie vvodimogo poglotitelja proishodit za schet sily tjazhesti, i polnyj vvod sterzhnja na 61 sm zanimaet 0,4 sek. Na otdeljonie ot magnita uhodit 5 millisekund. Poglotitel' vesit 7 kg, jeffektivnaja ploshhad' kadmija sostavljaet. 1000 cm{sup 2} , i on kontroliruet pochti 3% reaktivnosti. On mozhet byt' ustanovlen na mesto s. tochnost'ju do 4 x 10{sup -3}cm i izvlechen so skorost'ju 0,04 sm/sek i 0,01 sm/sek. Mehanizm sostoit iz stupenchatogo noniusnogo motora, kotoryj privodit v dvizhenie hodovoj vint i podnimaet ili opuskaet plotno prignannuju cilindricheskuju zashhitnuju probku, na nizhnem konce kotoroj nahoditsja jelektromagnit; podderzhivajushhij trubchatyj poglotitel'. Vokrug poglotitelja imjojutsja bol'shie radial'nye zazory, i pri osvobozhdenii poglotitelja on svobodno padaet, hotja ostaetsja vjazkoe trenie zamedlitelja/ohladitelja do ego ostanovki stoporom central'nogo sterzhnja, prohodjashhim cherez hodovoj vint k amortizirujushhemu ustrojstvu s kol'cevoj pruzhinoj

  4. Annual report of the mechanics group; Godisnji izvestaj masinske grupe

    Energy Technology Data Exchange (ETDEWEB)

    Bratic, A [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    Planned maintenance and repair of fundamental reactor systems was done during planned shut down periods in 1965. For that reason there was no interruption of reactor operation caused by failures of the equipment. Planned repairs were concerned with: heavy water system, gas system, technical water system, distillation system, graphite cooling system, ventilation and heating systems and emergency power supply system in the reactor building. This report includes as well, the list of unplanned repairs. [Serbo-Croat] U 1965. godini vrsen je planski remont osnovnih agregata reaktorskih sistema u planiranim periodima stajanja reaktora, te nije doslo ni do kakvih duzih prekida rada reaktora usled kvarova na opremi. Planski remont obuhvatio je: sistem teske vode, gasni sistem, sistem tehnicke vode, sistem destilacije, sistem hladjenja grafita, sistem ventilacije i grejanja, transportne uredjaje, dizel agregata. Ovaj izvestaj sadrzi i listu vanplanskih remonta i popravki.

  5. Annual report of the group for maintenance of electrical equipment; Godisnji izvestaj elektro grupe

    Energy Technology Data Exchange (ETDEWEB)

    Rajic, M [Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    This report includes detailed description of repairs and revisions of the electrical equipment of the RA reactor which were done according to the annual plan during the periods when reactor was not operated. Unplanned repairs are part of this report as well. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis remontnih i revizionih radova na elektroopremi reaktora RA izvrsenih prema godisnjem planu u periodima kada reaktor nije radio. Vanplanski poslovi ukljucujuci popravke elektroopreme su takodje deo ovog izvestaja.

  6. RB Research nuclear reactor, 30 years of operation; Istrazivacki nuclearni reaktor RB, povodom 30 godina rada

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M; Stefanovic, D [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1988-06-15

    Paper describes utilization, modifications and changes of construction and control-safety systems done at the RB reactor during 30 years of operation. Experiments performed at the reactor are summarized, new reactor equipment is described and the future plans are shown. Rad prikazuje eksploataciju reaktora RB tokom 30 godina rada, modifikacije i izmene u konstruktivnim i upravljacko-sigurnosnim sistemima. Sumirani su eksperimenti izvedeni na njemu, prikazana je nova oprema i planovi za buduci rad.

  7. Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

    Energy Technology Data Exchange (ETDEWEB)

    Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

    1963-10-15

    defectos hallados: Reactor de Elk River. Se descubrieron grietas en parte del revestimiento superficial del recipiente del reactor; ello obligo a efectuar una serie de investigaciones y analisis, asi como ciertas reparaciones y modificaciones del recipiente. La insuficiente capacidad de separacion de vapor obligo a sustituir y modificar algunas piezas metalicas en el interior del recipiente del reactor. Central nucleoelectrica de Hallam. Debido al arrastre de helio, hubo que modificar los circuitos secundarios de sodio. La falla de un tubo del intercambiador de calor intermedio (sodio-sodio) obligo a llevar a cabo una serie de analisis para descubrir su causa y extraer y reparar el intercambiador. Central nucleoelectrica de Piqua. Durante la limpieza de las tuberias con agentes quimicos, se dallaron varias valvulas que fue preciso reparar o sustituir. Las fugas en el circuito del refrigerante organico y del vapor secundario provocaron demoras repetidas. Una vez concluidas las reparaciones e introducidas las modificaciones necesarias, se comprobo que las caracteristicas de rendimiento reales de cada uno de los tres reactores se ajustaban estrictamente a las previstas en el proyecto. (author) [Russian] Fakticheskij opyt, nakoplennyj vo vremya predehkspluatatsionnykh ispytanij trekh yadernykh ehnergeticheskikh ustanovok, postroennykh po demonstratsionnoj programme ehnergeticheskikh reaktorov Komissii po atomnoj ehnergii Soedinennykh Shtatov, pozvolyaet sdelat' nekotorye obobshcheniya v otnoshenii ehtoj fazy stroitel'stva i ehkspluatatsii ustanovok. Tri ustanovki, a imenno Ehlk-riverskij reaktor (ERR), Khehllemskaya yadernaya ehnergeticheskaya ustanovka (HNPF) i Pikuaskaya yadernaya ehnergeticheskaya ustanovka (PNPF), predstavlyayut tri razlichnykh tipa reaktorov: reaktor s kipyashej vodoj s estestvennoj tsirkulyatsiej, natrievo-grafitovyj reaktor i reaktor s organicheskim teplonositelem i zamedlitelem sootvetstvenno. Period predehkspluatatsionnykh ispytanij okhvatyvaet vremya

  8. Measurement of the effective resonance integral of natural uranium; Merenje efektivnog rezonantnog integrala prirodnog urana

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, V; Kocic, A [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-12-15

    Good understanding of the nuclear properties of the materials in the reactor core is essential for reactor operation. One of the fundamental properties is the resonance absorption of the fuel, which is directly included in the reactor calculation through resonance escape probability and influences the choice of the materials quality in the core. This paper describes the measurement of resonance absorption integral of the natural uranium as a function of the S/M ratio. Improved experiment planning and analysis of results, as well as improvement of the ROB-1 reactor oscillator device related to the interpretation of results and decrease of reactor drift variations during measurement enabled higher precision of results compared to previous experiments. Poznavanje osobina nuklearnih karakteristika materijala koji ulaze u jezgro nuklearnog reaktora predstavlja bitan faktor u njegovom rezimu rada. Jedna od osnovnih je svakako rezonantna apsorpcija goriva, cija velicina - preko faktora rezonantnog izbegavanja - direktno ulazi u proracun nuklearnih reaktora i utice na izbor kvaliteta materijala koji ga sacinjavaju. U radu se opisuje merenje rezonantnog apsorpcionog integrala prirodnog urana u funkciji odnosa S/M. Bolja postavka eksperimenta i interpretacija rezultata, s jedne strane, i poboljsanje uredjaja reaktorskog oscilatora ROB-1 /1/ u pogledu analize podataka i smanjenja promene drifta reaktora u toku merenja, s druge strane, daju znacaj ovom radu u pogledu dobijanja preciznijih rezultata u odnosu na ranije /2/ (author)

  9. Annual report of the group for maintenance of electronic equipment; Godisnji izvestaj elektronske grupe

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, B [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    Maintenance and repair of the RA reactor control and safety systems were uniformly distributed during the whole year and were done according to the annual plan. A series of repairs of he electronic equipment as well as exchange of electronic components and elec tonic tubes. The testing and calibration of control and protection circuits were done regularly according to the needs and operation state of the reactor and according to the instructions. Inspections, repairs and reconstructions well as operating characteristics of individual elements as well as complete electronic circuits during 1965 have shown da the systems of control and safety are still in good condition. Somewhat higher number of failures due to aging of electronic tubes is a regular consequence of equipment and instrumentation aging. [Serbo-Croat] Remontni radovi na opremi sistema za upravljanje i sigurnost reaktora RA ravnomerno su rasporedjeni tokom cele godine i obavljaju se prema planu remonta. Izvrsen je citav niz popravki elektronske instrumentacije, kao i zamena komponenti i elektronskih cevi. Sve kontrole ispravnosti i kalibracije lanaca za upravljanje i zastitu reaktora redovno su vrsene prema potrebi i u vezi sa radnim stanjem reaktora prema uputstvu za ove operacije. Pregledi, remonti i popravke kao i radne karakteristike pojedinih elemenata kao i kompletnih instrumentalnih kontrolnih lanaca u toku 1965. godine pokazali su da su sistemi upravljanja i sigurnosne zastite jos u dobrom stanju. Nesto veci broj kvarova usled starenja elektronskih cevi je normalna posledica starenja opreme i instrumentacije.

  10. Congenital Primary Pachydermoperiostosis and Striate Palmoplantar Keratoderma - a Case Report

    Directory of Open Access Journals (Sweden)

    Stojanović Slobodan

    2014-06-01

    Full Text Available Uvod. Pahidermoperiostoza (PDP predstavlja heterogeni sindrom za koji su karakteristične hipertrofi čne promene prvenstveno kože i kostiju ekstremiteta: pahidermija, klabing (clubbing prstiju šaka i stopala i hipertrofi čna osteoartropatija. Primarna pahidermoperiostoza − sinonim Turen−Solent−Goleov sindrom (Touraine-Solente-Golé (PPDP, ili primarna hipertrofi čna osteoartropatija (PHO, redak je nasledni poremećaj i predstavlja jedan od dva tipa hipertrofi čne osteoartropatije.

  11. Sindrom metaboličke inzulinske rezistencije i metabolizam ugljikohidrata

    OpenAIRE

    Metelko, Željko; Crkvenčić, Neva

    2004-01-01

    Stanje metaboličke inzulinske rezistencije jest nemogućnost ostvarenja biološkog učinka inzulina u koncentracijama koje su učinkovite u zdravih osoba. Utjecaj se primjećuje na metabolizmu glukoze, metabolizmu lipida, funkciji krvnih žila i trombocita te regulaciji autonomnoga živčanog sustava. Fizička neaktivnost, nepravilna prehrana i sedentarni način života značajno pridonose razvoju pretilosti, metaboličke inzulinske rezistencije i tipa 2 šećerne bolesti. Metaboličk...

  12. DOLOČITEV POVRŠINSKE NAPETOSTI Z METODO KAPILARNEGA DVIGA DVOFAZNIH SISTEMOV

    OpenAIRE

    Kravanja, Gregor

    2014-01-01

    Namen magistrske naloge je bil postavitev merilne naprave in razvoj nove metode merjenja površinske napetosti s kapilarnim dvigom dvofaznih sistemov v okolici kritične točke. Za pridobitev natančnih in primerljivih meritev je bilo potrebno poznati natančni notranji premer tankih kapilar. Določili smo ga z metodo laserskega tipanja na nemški koordinatni merilni napravi ZEISS tipa UMC-850 s pomočjo merilne programske opreme CALYPSO 5.1.4. Za merjenje ravnotežne višine smo uporabili računalniški...

  13. Pomen standardov v geodetski izmeri

    OpenAIRE

    Janež, Žiga

    2016-01-01

    Med geodetskim delom se mnogokrat srečamo s takšnimi ali drugačnimi normativnimi dokumenti in pravnimi predpisi. Normativni dokumenti praviloma predpisujejo geodetske protokole za zagotavljanje predpisanih natančnosti. V nalogi so obravnavani normativni dokumenti za dva tipa geodetskih meritev, bolj natančen pri pregradnih objektih ter manj natančen pri detajlni izmeri. Najprej so na splošno predstavljeni normativni dokumenti ter njihove značilnosti. Temu sledi pregled normativnih dokument...

  14. Predstave o seksu u filmovima na temu postapokalipse

    Directory of Open Access Journals (Sweden)

    Ana Banić-Grubišić

    2016-03-01

    Full Text Available Rad se bavi načinima predstavljanja seksualnih odnosa u filmovima na temu postapokalipse. Razmatraju se različiti oblici/vrste seksualnih veza, koje se javljaju u postkataklizmičnom okruženju, u odnosu na dva tipa zajednica/društava koja nastaju nakon kraja sveta. Ti filmovi pokazuju koliko je ideja o nagonskoj, prirodnoj, biološkoj seksualnosti raširena u popularnoj imaginaciji – seks je u postapokalipsi predstavljen kao pokretačka sila, na isti način kao što je to i glad.

  15. Gas-flow detector for uranium contamination on finned-can surface of a reactor fuel; Detecteur a courant gazeux pour deceler la contamination en uranium des nervures des gaines de combustible nucleaire; Gazopotochnyj detektor zagryazneniya uranom rebristoj poverkhnosti obolochki reaktornykh teplovydelyayushchikh ehlementov; Detector de flujo gaseoso para medir la contaminacion de uranio en la superficie de la vaina de aletas de los elementos combustibles para reactores

    Energy Technology Data Exchange (ETDEWEB)

    Miwa, H; Shiojiri, T; Maeda, Y [Kobe Kogyo Corporation, Okubo, Akashi, Hyogo (Japan)

    1962-04-15

    stavitsya pod otritsatel'noe napryazhenie. Prostranstvo mezhdu toplivnym ehlementom i setkoj sluzhit ulovitel'noj ionizatsionnoj kameroj. Setka sostoit iz parallel'nykh vol'framovykh provodov, zazemlennykh i raspolozhennykh tsilindricheski vokrug toplivnogo ehlementa. Kollektory sostoyat iz 16-ti tonkikh vol'framovykh provolochek, skonstruirovannykh analogichno setke, no kazhdaya provoloka izolirovana ehlektricheski ot drugikh. Vse kollektory soedineny mezhdu soboyu cherez soprotivleniya v 50 kiloomov i cherez pitayushchee soprotivlenie vklyucheny v set' s polozhitel'nym tokom vysokogo napryazheniya. Prostranstvo mezhdu setkoj, kollektorami i katodom sluzhit v kachestve gazovoj umnozhitel'noj kamery, podobno obychnomu proportsional'nomu schetchiku. Kazhdoe soprotivlenie v 50 kiloomov otdelyaet parazitnuyu emkost' podklyuchennogo kollektora ot drugikh emkostej. Vykhodyashchij iz detektora signal napravlyaetsya v usilitel' toka s malym vkhodnym kompleksnym soprotivleniem. Maloe vkhodnoe kompleksnoe soprotivlenie snizhaet takzhe vrednoe vliyanie parazitnoj emkosti vkhodyashchej skhemy. Ehto vedet k polucheniyu khoroshego sootnosheniya signal-pomekha i povyshaet chuvstvitel'nost' obnaruzheniya al'fa-chastits. Do proizvodstva izmerenij v schetchike predvaritel'no sozdaetsya vakuum otkachivaniem pri pomoshchi rotatsionnogo nasosa, posle chego v nego nagnetaetsya gaz PR (90% argona i 10% metana). Blagodarya ispol'zovaniyu ehtogo novogo oborudovaniya nam udalos' obnaruzhit' al'fa-chastitsy, ispuskavshiesya 1 x 10{sup -5} g prirodnogo urana, zagryaznyavshego rebristuyu poverkhnost' obolochki reaktornykh teplovydelyayushchikh ehlementov tipa Kvl'der-Kholl; vse teplovydelyayushchie ehlementy reaktora JRR-3 budut provereny ehtim schetchikom. (author)

  16. Report on results of the Experts from the Boris Kidric Institute to the Institute for theoretical and experimental physics in Moscow - Operational Report; Radni izvestaj - Izvestaj o rezultatima posete strucnjaka iz IBK Institutu za teorijsku i eksperimentalnu fiziku u Moskvi

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Petrovic, M; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    .) upoznavanje eksploatacionih karakteristika reaktora TVRS sa 80% obogacenim gorivom, kao i iskustva u vezi sa koriscenjem tog goriva u reaktoru TVRS u Moskvi; b.) upoznavanje sa elementima sigurnosnih analiza u vezi sa uvodjenjem i kriscenjem tog goriva u reaktoru TVRS kao i c.) razmena gledista o programu prevodjenja reaktora RA na novo 80% obogaceno gorivo. U izvestaju su prikazani rezultati ove posete. Osnovni zakljucci do kojih se doslo jesu: a.) poseta je bila korisna i pored toga sto na neka pitanja nije dobijen odgovor; b.) posle obrade dobijenih informacija, posle sticanja prvih iskustava o koriscenju novog goriva u reaktoru RA kao i posle donosenja definitivnog suda o ravnoteznom rezimu reaktora RA sa novim gorivom, bilo bi veoma korisno da se izvrsi jos jedna poseta Institutu u Moskvi; c.) novo disperziono gorivo je mnogo pouzdanije u eksploataciji od starog 2% obogacenog metalnog goriva (kakvo je sada u reaktoru RA); d.) nije bilo primedbi sa aspekta sigurnosti na nas program prevodjenja (prelazni rezim) reaktora RA na novo gorivo; e.) zatrazice se dopunske informacije o maksimalnom dopustivom stepenu izgaranja 80% obogacenog disperzionog goriva i po potrebi izvrsice se blagovremena revizija predvidjenog optimalnog ravnoteznog rezima izgaranja za reaktor RA (baziranog na maksimalnom izgaranju goriva koje omogucuju parametri reaktora RA); f.) metodologija termickog proracuna gorivnih kanala, koja se primenjuje na reaktor RA ocenjena je kao ekvivalentna postupku koji se primenjuje za proracun kanala reaktora TVRS u Moskvi (author)

  17. Report on the activity of the RA reactor operation for the period from July 1 1961 - Sept. 30 1961; Tromesecni izvestaj za period od 1.VII do 30.IX 1961. g

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Laboratorija za eksploataciju reaktora RA, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-09-15

    During the reporting period the reactor was permanently ready for operation and responding to the demands of the experimenters. The reactor was operating for 408.5 hours at power levels from 50 - 5000 kW, or 1985 MWh in total, burnup of the first batch of fuel was 22.55%. Reactor core was made of 56 fuel channels. Activities related to construction of new and improvement of the existing equipment was continued in order to enable safe operation and successful utilization of the RA reactor. Exchange of the electronic tubes was continued in order to increase the stability of the reactor control and reactor protection systems. About 65% of tubes planned to be exchanged this year was done. Cooperation with the CEN Saclay, France related to construction of experimental loops VISA-1 and VISA-2 was continued as well as cooperation with Poland concerned with exchange of experts. The problem of lack of properly trained staff was nor solved. [Serbo-Croat] U izvestajnom periodu reaktor je uvek bio spreman za rad i odgovarao je zahtevima eksperimentatora. Reaktor je radio 408,5 casova na snagama od 50-5000 kW, odnosno ukupno 1985 MWh, pri cemu je ukupan utrosak prve sarze goriva bio 22,55%. Jezgro reaktora bilo je sacinjeno od 56 tehnoloskih kanala. Radi bezbednijeg pogona i sto uspesnije eksploatacije reaktora RA nastavljeno je sa radovima na realizaciji novih i poboljsanju postojecih uredjaja. U cilju povecanja stabilnosti elektronskih instrumenta u sistemu upravljanja i zastiti reaktora nastavljeno je sa zamenom elektronskih cevi, do sada je zamenjeno oko 65% radova predvidjenih za ovu godinu. Nastavljena je saradnja sa nuklearnim centrom u Saclay, Francuska na izradi petlje VISA-1 i VISA-2 i saradnja sa Poljskom u razmeni strucnjaka. Problem nedostatka kadrova nije resen.

  18. Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Cupac, S; Vukadin, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    This annex covers: description of the organisational structure of the service, safeguard activities, increase of reactor operation capability, dosimetry and radiation protection tasks and an overview of the the activities of this Service. During 1992, there have been 12 safeguard IAEA inspections. Each time inspection covered fresh fuel, every third inspection included control of the spent fuel storage pool, and once during the fuel inventory control the reactor core was included. With the aim of increasing the operating capabilities besides improvement of experimental devices, construction of the experimental loop with separate cooling system was started. It is planned, as well to improve operating capabilities of horizontal experimental channels by purchasing neutron diffractometer, constructing three-crystal neutron spectrometer, application of three-crystal neutron spectrometer from Krakow, and using the time-of flight spectrometer constructed in the Institute. This Annex describes the possible activities for neutron radiography and isotope production, and includes radiation protection data. [Serbo-Croat] Ova prilog sadrzi opis organizacije tehnoloske sluzbe, 'safeguard' aktivnosti, moguce poboljsanje eksploatacionih mogucnosti reaktora, tehnicke zastite od zracenja i dozimetrije, kao i pregled svih poslova Sluzbe. Tokom 1992. bilo je 12 'safeguard' IAEA inspekcija. Tokom svake inspekcije kontrolisano je sveze gorivo, svaka treca je ukljucila kontrolu bazena za odlezavanje ozracenog goriva, a jednom je kontrolisano i jezgro reaktora RA. Sa ciljem da se poboljsaju operativne mogucnosti reaktora, pored poboljsanja eksperimentalnih uredjaja, pocela je i izgradnja reaktorske petlje sa sopstvenim hladjenjem. Planirano je da se poboljsaju i operativne mogucnosti horizontalnih eksperimentalnih kanala, sto je ucinjeno kupovinom neutronskog difraktometra, izgradnjom trikristalnog neutronskog spektrometra, koriscenjem trikristalnog neutronskog spektrometra koji je

  19. Operational report, Advantages of gradual introducing of highly enriched fuel into the RA reactor core from economic aspect and users needs; Radni izvestaj, Prednost postupka parcijalnog uvodjenja visokoobogacenog goriva u reaktor RA sa aspekta ekonomicnosti i potreba korisnika

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-10-14

    The possibility of increasing the neutron flux in the RA reactor was considered for a number of years. The possibilities of reactor reconstruction are not realistic and they should be disregarded. The possibility that remains is to achieve higher neutron flux by improving the fueling scheme and above all by introducing highly enriched fuel into the reactor core. Decision to purchase highly enriched fuel was quicker due to the fact that the 2% enriched uranium fuel is not fabricated any more. There are two procedures for exchanging the fuel in the reactor core: a) removal of partially spent 2% enriched fuel and formation of the core with fresh highly enriched fuel; b) gradually introducing the new fuel into the existing RA reactor core according to a special transfer regime. This report includes some comparative analyses of these two procedures from both economic point of view and the needs of users, as well as some technical conditions. These results are in favour of gradual introducing of new fuel into the reactor core. relevant direct savings amount to 3 000 000 dinars. Some of the most important advantages cannot be estimated in this way. This report does not cover the safety analyses results which are presented in a series of other papers. [Serbo-Croat] Vec vise godina razmatra se mogucnost za povecanje neutronskog fluksa u reaktoru RA. Mogucnosti za rekonstrukciju reaktora RA u tom smislu su minimalne i realno ih treba odbaciti. Prema tome preostaje da se povecanje neutronskog fluksa postigne usavrsavanjem seme izmene goriva, a pre svega uvodjenjem goriva sa visokim stepenom obogacenja u reaktor RA. Donosenje odluke o nabavci visokoobogacenog goriva i njegovom uvodjenju u reaktor ubrzano je i cinjenicom da se staro 2% obogaceno uransko gorivo vise ne proizvodi. Postoje dva postupka za prevodjenje reaktora na ovo gorivo: a) Uklanjanjem poluistrosenog 2% obogacenog goriva iz reaktora i formiranjem jezgra iskljucivo od svezeg visokoobogacenog goriva, b

  20. RA research reactor - properties and experimental capabilities; Istrazivacki reaktor RA - Tehnicke karakteristike i eksploatacione mogucnosti

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M; Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-05-15

    The brief survey of the Reactor RA exploitation experience, as well as the reactor equipment state, after 18 years of operation is presented. The results of efforts spent on reactor characteristics improvement in order to ensure safe and reliable reactor operation for next 15-20 years, are described. Prikazani su fragmenti iz eksploatacije reaktora kao i stanje opreme, posle 18 godina rada. Na kraju je dat prikaz sta je preduzeto i sta se preduzima da se poboljsaju karakteristike i poveca sigurnost i bezbednost rada za sledecih 15-20 godina.

  1. Program of critical experiment and measurements at the RA reactor; Program kriticnih eksperimenata i merenja na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-14

    Program described in this document describes in detail the following experiments: critical experiments with two reactor core lattices with 38 and 44 fuel channels, initial heavy water level being 1300 mm, criticality is achieved by adding heavy water; preliminary analysis of heavy water quality and verification of the fuel isotopic contents; experiment with the initial core which contains 56 fuel channels with maximum heavy water level according to the Russian proposal; measurement of neutron flux by Dy and In foils; measurement of reactivity excess dependent on the heavy water level and number of fuel rods; measurement of reactor period for determined reactivity change; measurement of moderator temperature coefficient; measurement of absolute flux. [Serbo-Croat] Program sadrzan u ovom dokumentu opisuje detaljno sledece eksperimente: kriticni eksperiment sa dve konfiguracije jezgra reaktora, sa 38 i 44 gorivna kanala, pocetni nivo teske vode je 1300 mm, kriticnost se dostize dodavanjem teske vode; prethodno izvrsenom analizom teske vode i proverom izotopskog sastava goriva; eksperiment sa pocetnom resetkom koja prema ruskom predlogu sadrzi 56 gorivnih kanala i maksimalnom visinom teske vode; merenje raspodele neutronskog fluksa folijama Dy i In; kalibracija regulacionih sipki; merenje viska reaktivnosti sa promenom visine nivoa teske vode i promenom broja sipki; merenje periode reaktora za odredjenu promenu reaktivnosti; merenje temperaturnog koeficijenta za vodu; merenje apsolutnog fluksa.

  2. Methods for measuring nuclear properties of materials, Safety coefficient method and measurement of effective absorption coefficient of graphite by safety coefficient method; Razvijanje metoda merenja nuklearnih karakteristika materijala, Razrada metode koeficijenta opasnosti i merenje efektivnog apsorpcionog preseka grafita metodom koeficijenta opasnosti

    Energy Technology Data Exchange (ETDEWEB)

    Maglic, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-11-15

    Reactivity of a reactor depends on production, absorption and leaking of neutrons. Change of absorption causes reactivity change, and this fact is used for determining the neutron absorption cross section for the sample inserted in the reactor core. Method for determining the absorption cross section based on reactivity change is called method of safety coefficient. Measurements of neutron absorption cross section for graphite was done in the RA reactor vertical experimental channel VK-5. taking into account the results obtained for five types of graphite this method is considered to be reliable for use. Comparison of nuclear properties of different types of graphite was done as well. Reaktivnost reaktora zavisi od proizvodnje neutrona, apsorpcije i isticanja neutrona. Promena apsorpcije izaziva promene reaktivnosti reaktora pa se ova osobina koristi za odedjivanje neutronskog apsorpcionog preseka uzorka koji se unosi u reaktor. Metoda merenja apsorpcionog preseka na bazi promene reaktivnosti nazvana je metodom koeficijenta opasnosti. Merenje apsorpcionog preseka grafita uradjeno je na reaktoru RA u vertikalnom eksperimentalnom kanalu VK-5. S obzirom na rezultate koji su dobijeni za pet vrsta grafita moze se smatrati da je opravdano koriscenje ove metode. Izvrseno je i poredjenje nuklearnih osobina pomenutih tipova grafita.

  3. RA Research reactor, Annual report 1972; Istrazivacki nuklearni reaktor RA - Izvestaj za 1972. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1972-12-15

    During 1972, the total production was 31151 MWh which is 3.8% higher than planned. The reactor was used for irradiation and experiments according to the demand of 381 users, of which 340 from the Institute and 41 external users. This report contains detailed data about reactor power and experiments performed in 1972. Discrepancies from the action plan, meaning higher production was achieved due to special demands of the users. Total number of interruptions was lower than during all the previous years, and were caused mainly due to announced power cuts. There was only on scram shutdown during this year caused by a false signal of the reactor control instrumentation. There were no longer interruptions. One shorter interruption (shorter than 24 hours) caused by removal of a UO{sub 2} capsule from the core, placed there for measuring heat transfer. Total personnel exposure dose was lower than during previous years. One accident caused contamination with gases and aerosols containing mainly shot-living isotopes. Decontamination od surfaces was less than during previous years. Practically there was no surface contamination that would demand action of the decontamination team, except for the regular decontamination after refueling. It was concluded that the successful operation in 1972 has a special significance having taking in account the financial crisis caused by the unresolved status of the reactor. It is emphasised, in the plan for the next year that there is an urgent need of making a long-term plan of rector application. It is indispensable to finish preparatory tasks for replacing the fuel with the highly enriched fuel elements by 1974, and building the core emergency cooling system. [Serbo-Croat] Ukupni rad Reaktora RA je u 1972. godini iznosio je 31151 MWh odnosno 3,8% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimente za 381 korisnika od cega 340 iz Instituta i 41 za korisnike izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i

  4. Research nuclear reactor RA - Annual Report 1991; Istrazivacki nuklearni reaktor RA - Izvestaj za 1991. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Construction of some support elements is almost finished by the local staff. The Institute has undertaken this activity in order to speed up the ending of the project. If all the planned instrumentation would not arrive until the end of March 1992, it would not be possible to start the RA reactor testing operation in the first part of 1993, as previously planned. In 1991, 53 staff members took part in the activities during 1991, which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1991. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci

  5. Geomorfološke značajke Dugog otoka

    Directory of Open Access Journals (Sweden)

    Katarina Džaja

    2003-01-01

    Full Text Available Dugi otok je najveći (114 km2 i najduži otok (44,4 km zadarskog arhipelaga. Prema razvedenosti obalne crte (4,5 drugi je na Jadranu. Glavne geomorfološke karakteristike otoka su relativno velika podudarnost orografije s temeljnim geološkim strukturama i prevlast krškog tipa reljefa na karbonatnoj litološkoj osnovi. Bitan je i marinski tip reljefa, odnosno abrazijski proces. Usporednost otoka s temeljnim reljefnim i geološkim strukturama susjednog kopna svrstava otok u tip kontinentskih otoka izduženih dinarskim pravcem pružanja SZ-JI. Današnje reljefne značajke su posljedica poslijepleistocenske ingresije mora kada se svjetska morska razina izdigla oko 100 m.

  6. FIZIČKA AKTIVNOST I ŠEĆERNA BOLEST

    OpenAIRE

    BARETIĆ, MAJA

    2017-01-01

    Sve veća učestalost šećerne bolesti povezuje se s prihvaćanjem netradicionalnih načina prehrane i prakticiranjem „sjedilačkog načina života“. Liječenje šećerne bolesti sastoji se od promjene životnog stila što uključuje promjenu fizičke aktivnosti, tipa i učestalosti prehrane te uzimanje specifi čne terapije. Fizička aktivnost je dio temeljnog liječenja dijabetesa; ima dokazane koristi u smanjenju inzulinske rezistencije, poboljšanju glikemijske kontrole, lipidnog profi la, u normalizaciji tj...

  7. Irradiation and study of irradiated full elements and sintered UO{sub 2} fuel; Ozracivanje i ispitivanje ozracenih gorivnih elemenata i goriva na bazi sinterovanog UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    This review contains the activities related to the development of UO{sub 2} fuel elements, based on study of the processes in the fuel. This work was done during development, irradiation and testing of certain type of fuel rods and fuel assemblies. A feasibility study for irradiation of fuel elements in our country or abroad was done by analysing the defined problem and our capabilities in this field. Izlozen je pregled potrebnih radova na ozracivanju vezanih za razvoj gorivnih elemenata sa UO{sub 2} gorivom, prikazan kroz rad na osnovnim usmerenim istrazivanjima procesa i pojave u gorivu, kroz razvoj odredjenog tipa gorivnih elemenata ozracivanjem i ispitivanjem ozracenih gorivnih sipki i sklopova gorivnih elemenata. Na osnovu tako postavljenog problema i nasih mogucnosti za rad na ovom polju izvrsena je analiza celishodnosti ozracivanja gorivnih elemenata (goriva) kod nas, odnosno u inostranstvu (author)

  8. Antioksidacijska svojstva i stabilnost boje tijekom ubrzanog i prirodnog starenja piva tamnih piva

    OpenAIRE

    Herceg, Filip

    2015-01-01

    Pivo je piće dobiveno alkoholnom fermentacijom sladovine, većinom pripravljene samo od ječmenog slada, no mogu se dodati i neslađene žitarice, kao što su kukuruz, pšenica ili riža. Smatra se dobrim izborom polifenola kojima je izvorište u ječmenom sladu i hmelju. U ovom je radu određivan oksidacijski profil dva različita tipa hrvatskih tamnih piva podvrgnutih ubrzanom postupku starenja (6 dana pri 42 oC) i prirodnom starenju (4 mjeseca pri sobnoj temperaturi). U uzorcima su određivani udjel u...

  9. Relaciones isotópicas Sm/Nd en rocas graníticas y miloníticas de Sierras Pampeanas del noroeste Argentino

    Directory of Open Access Journals (Sweden)

    Kawashita, K.

    2005-04-01

    Full Text Available The Velasco, Copacabana and Paimán Ranges in Sierras Pampeanas, are constituted mainly by paleozoic plutonic bodies of the Famatinian cycle (Huaco, Antinaco and Paimán and for mylonitic rocks (TIPA Shear Zone, originated as a consequence of dynamic events happening during the Upper Ordovician-Devonian. The last magmatic event of the area would probably have of devonian age (Granite San Blas. Model-ages of two stages were calculated based on 147Sm/144Nd relationships; the obtained values are closely grouped at around 1594 Ma. and the more plausible interpretation seems to be a reworking of an Early Proterozoic protolith.Las sierras de Velasco, Copacabana y Paimán, en el ambiente de Sierras Pampeanas, están constituidas principalmente por cuerpos plutónicos del Paleozoico inferior, relacionados con el ciclo Famatiniano (Granitos Huaco, Antinaco y Paimán y por rocas miloníticas (Faja Milonítica TiPA, originadas a partir de estos protolitos como consecuencia de eventos dinámicos acaecidos durante el Ordovícico superior-Devónico. El último evento magmático del área es de edad probablemente devónica (Granito San Blas. Se calcularon edades modelos de «dos estadios» en base a relaciones 147Sm/144Nd; los valores obtenidos se presentan estrechamente agrupadas en torno a 1594 Ma. y se interpretan a este basamento como un protolito del Proterozoico medio retrabajado.

  10. Modeling Interdependent and Periodic Real-World Action Sequences

    Science.gov (United States)

    Kurashima, Takeshi; Althoff, Tim; Leskovec, Jure

    2018-01-01

    Mobile health applications, including those that track activities such as exercise, sleep, and diet, are becoming widely used. Accurately predicting human actions in the real world is essential for targeted recommendations that could improve our health and for personalization of these applications. However, making such predictions is extremely difficult due to the complexities of human behavior, which consists of a large number of potential actions that vary over time, depend on each other, and are periodic. Previous work has not jointly modeled these dynamics and has largely focused on item consumption patterns instead of broader types of behaviors such as eating, commuting or exercising. In this work, we develop a novel statistical model, called TIPAS, for Time-varying, Interdependent, and Periodic Action Sequences. Our approach is based on personalized, multivariate temporal point processes that model time-varying action propensities through a mixture of Gaussian intensities. Our model captures short-term and long-term periodic interdependencies between actions through Hawkes process-based self-excitations. We evaluate our approach on two activity logging datasets comprising 12 million real-world actions (e.g., eating, sleep, and exercise) taken by 20 thousand users over 17 months. We demonstrate that our approach allows us to make successful predictions of future user actions and their timing. Specifically, TIPAS improves predictions of actions, and their timing, over existing methods across multiple datasets by up to 156%, and up to 37%, respectively. Performance improvements are particularly large for relatively rare and periodic actions such as walking and biking, improving over baselines by up to 256%. This demonstrates that explicit modeling of dependencies and periodicities in real-world behavior enables successful predictions of future actions, with implications for modeling human behavior, app personalization, and targeting of health interventions. PMID

  11. On the functions and grammatical status of the Latvian modal particle lai

    Directory of Open Access Journals (Sweden)

    Axel Holvoet

    2011-11-01

    Full Text Available PAR MODĀLĀS PARTIKULAS lai FUNKCIJĀM UN GRAMATISKO STATUSUKopsavilkumsLatviešu valodas gramatikās partikula lai parasti tiek minēta tikai kā analītisko imperatīva formu sastāvdaļa (lai nāk, lai neaizmirstam. Šai rakstā tiek aplūkoti trīs partikulas lai lietošanas tipi: (1 teikumos ar pamudinājuma vai vēlējuma nozīmi (Lai viņi nāk, (2 deontiskajos jautājumos (Ko lai es daru! Ko lai es būtu darījis!, un (3 teikumos ar vērtējuma (neaprobēšanas vai šaubu nozīmi (Viņš lai būtu palīdzējis slepkavām?. Autors cenšas parādīt, ka pirmā (dažreiz arī otrā tipa teikumos partikulai lai piemīt teikuma partikulas īpašības, kamēr otrā un trešā tipa teikumos iezīmējas tendence šai partikulai veidot ar verbu ciešāku sakopojumu, kas gan nelīdzinās analītisko verbu formu statusam, bet zināmā mērā atgādina savienojumus ar modālajiem verbiem. ‘Formveidojošas partikulas’ statusa, ko partikulai lai piedēvē gramatikās, šim vārdam nav nekur.

  12. Analiza rezultata određivanja sadržaja stabilizatora u prirodno starenim barutima / Content of stabilizer determination results analysis of naturally aged gun propellants

    Directory of Open Access Journals (Sweden)

    Luka Grbović

    2006-04-01

    Full Text Available Praćenje sadržaja stabilizatora jedna je od suvremenih i pouzdanih metoda koja se u svetu, a i kod nas, primenjuje za kontrolu kemijske stabilnosti i prognoziranje veka upotrebljivosti baruta. Radi ocene kemijske stabilnosti baruta domaće proizvodnje u radu su analizirani rezultati određivanja sadržaja stabilizatora u prirodno starenim jednobaznim barutima tipa NC i NCD i dvobaznim barutima tipa NGB i NGH. Pri tome su uporedno analizirani rezultati uzoraka iz kolekcija baruta iz Kragujevca (KB-1 i Zelenike (KB-2. Dobijeni rezultati ukazuju na znatno brži pad stabilnosti uzoraka baruta iz kolekcije KB-2, što se može objasniti značajnim uticajem klimatskih uslova. Osim toga, dobijeni rezultati potvrđuju uticaj mnogih faktora na kemijsku stabilnost baruta, kao što su: sastav, kvalitet sirovina, tehnološki postupak, oblik i dimenzije barutnog zrna i sl. / Monitoring of the stabilizer content is one of the modern and reliable methods in the world, and here also, which is used to control chemical stability and to predict the usage time of gun propellants. For the purpose of evaluation of gun propellants' chemical stability manufactured in our country, in this paper -we analyzed results from the content of stabilizer determination in naturally aged single base, NC and NCD type, and double base, NGB and NGH type of gun propellants. At the same time -we analyzed results from both collections of gun propellant samples, one from Kragujevac factory (KB-1 and the other from Zelenika factory (KB-2. Obtained results point that the stability decays faster for KB-2 collection samples, -which can be explained due to climate factors. Beside this influence, obtained results prove the influence of many factors on chemical stability of gun propellants: used components, quality of the ingredients, procedures of manufacture, shape and dimensions of gun propellant grains, etc.

  13. Research nuclear reactor RA - Annual Report 1997; Istrazivacki nuklearni reaktor RA - Izvestaj za 1997. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1997-12-01

    RA reactor is not in operation since 1984, activities related to revitalisation of the RA reactor started in 1986. The planned actions related to renewal of the reactor components were finished except for the most important action, related to exchange of complete reactor instrumentation which was delayed. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the sanctions imposed to our country. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 42 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1997 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Reaktor RA nije u pogonu od 1984, aktivnosti na revitalizaciji, rekostrukciji i modernizaciji reaktorski sistema zapocete su 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Do septembra 1991. godine isporuceno svega 80% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju usled sankcija uvedenih od strane organizacije Ujedinjenih nacija. Demontirana je postojeca instrumentacija. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Kontrola goriva od strane safeguard inspektora MAAE obavljana

  14. Research nuclear reactor RA - Annual Report 1996; Istrazivacki nuklearni reaktor RA - Izvestaj za 1996. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1996-12-01

    Activities related to revitalisation of the RA reactor started in 1986, were continued in 1996. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 43 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1996 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U toku 1996. godine nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport. Prema tom

  15. Research nuclear reactor RA - Annual Report 1995, with comparative review for period 1991-1995; Istrazivacki nuklearni reaktor RA - Izvestaj za 1995. godinu, uz uporedni pregled za period 1991-1995

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1995-12-01

    Activities related to revitalisation of the RA reactor started in 1986, were continued during period 1991-1995. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved during the period 1991-1995. This research reactor RA Annual is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U periodu 1991-1995. godina nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom

  16. RA reactor operation and maintenance in 1992, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktoro RA u 1992. Godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Tanaskovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-12-01

    During 1992 Ra reactor was not in operation. All the activities were fulfilled according to the previously adopted plan. Basic activities were concerned with revitalisation of the RA reactor and maintenance of reactor components. All the reactor personnel was busy with reconstruction and renewal of the existing reactor systems and building of the new systems, maintenance of the reactor devices. Part of the staff was trained for relevant tasks and maintenance of reactor systems. [Serbo-Croat] U toku 1992 godine poslovi u okviru projekta 'Istrazivacki nuklearni reaktor RA' obavljani su u skladu sa programom i planom rada. Osnovne aktivnosti na kojima je radjeno odnosile su se na revitalizaciju reaktora RA, kao i na odrzavanje opreme. U ovom periodu reaktor nije bio u pogonu. Svo osoblje je bilo angazovano na poslovima rekonstrukcije i modernizacije postojecih i dogradnje novih reaktorskih sistema, na odrzavanju opreme a deo tehnickog osoblja je bio obucavan za vrsenje odgovarajucih poslova u pogonu i odrzavanju opreme.

  17. Heat conductance of sintered UO{sub 2}; Toplotna provodljivost sinterovanog UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Katanic-Popovic, J; Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    Phenomena influencing the heat conductance of the sintered UO{sub 2} were analyzed, first of all when used as nuclear fuel. Influence of temperature, density and porosity, additives and irradiation in the reactor are shown. Based on the available literature, the measured heat conductance values were analyzed for the sintered UO{sub 2} outside the reactor and in the reactor during irradiation. Analizirane su pojave koje uticu na toplotnu provodljivost sinterovanog UO{sub 2}, pre svega, sa aspekta njegove primene kao goriva. Izlozen je uticaj temperature, gustine i poroznosti, aditiva i ozracivanja u reaktoru. Na osnovu pregleda dostupne literature kriticki su prikazani rezultati merenja toplotne provodljivosti sinterovanog UO{sub 2} van reaktora i u reaktoru pri ozracivanju (author)

  18. A review of calculation methods for fast and intermediate reactors; Expose des methodes pour le calcul de reacteurs a neutrons rapides et intermediaires; Obzor metodov rascheta reaktorov na promezhutochnykh i bystrykh nejtronakh; Estudio panoramico de los metodos de calculo de los reactores rapidos e intermedios

    Energy Technology Data Exchange (ETDEWEB)

    Marchuk, G I [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    de ecuaciones fundamentales y conjugadas de la teoria de los multigrupos. Expone luego diversas aplicaciones de la teoria de la perturbacion a los problemas del calculo fisico del reactor. Examina los metodos numericos de resolucion de las ecuaciones fundamentales y conjugadas que expresan el funcionamiento del reactor sobre la base del metodo de los armonicos esfericos. Explica asimismo como se utiliza el metodo de las caracteristicas en la solucion de problemas relativos a la masa critica del reactor. Describe los metodos de calculo de los reactores con moderadores que contienen hidrogeno y, por fin, expone las bases de un modelo efectivo fundado en la teoria de un solo grupo, aplicable al reactor. (author) [Russian] Obsuzhdaetsya razvitie metodov rascheta yadernykh reaktorov na promezhutochnykh i bystrykh nejtronakh. Rassmatrivayuts ya razlichnye postanovki zadach fizicheskogo rascheta. Obsuzhdaetsya uchet rezonansnykh ehffektov. Vvodyatsya v rassmotrenie mnogogruppovy e sistemy 'osnovnykh i sopryazhennykh uravnenij. Daetsya razlichnoe primenenie teorii vozmushchenij k zadacham fizicheskogo rascheta reaktora. Rassmatrivayuts ya chislennye metody resheniya osnovnykh i sopryazhennykh uravnenij reaktora v priblizhenii metoda sfericheskikh garmonik. Daetsya primenenie metoda kharakteristik k resheniyu zadach na kriticheskuyu massu reaktora. Izlagayutsya metody rascheta reaktorov s vodorodsoderzhashchim i zamedlitelyami . Izlagayutsya osnovy ehffektivnoj odnogruppovoj modeli reaktora. (author)

  19. Annex 3 - Testing the microstructure of the fuel element with metal uranium with aluminium cladding; Prilog 3 - Ispitivanje mikrostrukture gorivnog elementa na bazi metalnog urana sa aluminijumskom kosuljicom

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, S; Momcilovic, I [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Based on the uranium microstructure in the fuel element, i.e. grain size, presence of other phases, porosity and the position of metal connections, some data could be obtained about the mechanical and thermal treatment of the uranium during fuel element fabrication. The mentioned characteristics could indicate the behaviour of the fuel under reactor operating conditions taking into account its stable dimensions and roughness of its surfaces. Na osnovu mikrostrukture urana u gorivnom elementu, odnosno velicine i oblika njegovih kristalnih zrna, prisustva drugih faza, pozoziteta kao i rasporeda metalnih ukljucaka, mogu se dobiti izvesni podaci o tome koje je postupke mehanickog i termickog tretiranja pretrpeo uran u pripremi za gorivni elemenat. Prethodne karakteristike takodje mogu da daju predstavu o tome kako ce se gorivo ponasati u uslovima rada reaktora, s obzirom na njegovu dimenzionu stabilnost i ogrubljivanje njegove povrsine (author)

  20. Definition of task (Phase II) B, 'Leak testing'; Definicija zadatka (II faza) B, 'Ispitivanje hermeticnosti'

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    In order to ensure safe Ra reactor operation and fulfilling the conditions for performing irradiation experiments it was necessary to test and verify the leak tightness of the sample containers and thermocouples, as well as the irradiation capsule before it was placed in the VISA-2 channel. Leak testing of VISA-2 channel with capsules and thermocouples was done before and after it was built-in the reactor. [Serbo-Croat] U cilju bezbednosti i sigurnosti rada reaktora RA i ispunjavanja uslova ozracivanja izvrsena je provera hermeticnosti kenera sa uzorcima i termoparovima, kao i hermeticnost kapsule pre ugradjivanja kapsule u kanal VISA-2. Izvrseno je i ispitivanje hermeticnosti kanala VISA-2 sa kapsulama i termoparovima pre ugradjivanja u reaktor i posle montaze.

  1. Technical realisation of the VISA-II Project, Phase II, Chapter X, Vol. VI; Tehnicka realizacija projekta VISA-II, II faza, Glava X, Album VI

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    The second phase of the 'Project VISA-2 described in this chapter of Vol. VI includes the project specifications and technical drawings of the 'measuring system of VISA-2 for testing the VISA-2 channels outside and in the reactor'. In addition to the task objective, description of the measuring system, action plan, description of the work done it contains the definition of the task 'Leak testing' and instructions for the instrumentation personnel on duty. [Serbo-Croat] Druga faza zadatka {sup T}ehnicka realizacija projekta VISA-2' opisana u ovom poglavlju Albuma VI, sadrzi tehnicki opis i crteze 'Mernog sistema VISA-2 i ispitivanje kanala VISA-2 van reaktora i u reaktoru'. Pored definicije zadatka, opisa mernog sistema VISA-2, razrade zadatka, tekstualnog dela projekta i opisa izvedenih radova, ovo poglavlje obuhvata definiciju i razradu podzadatka 'Ispitivanje hermeticnosti' i dodatak sa instrukcijama za dezurne instrumentatore u vezi eksperimenta VISA-2.

  2. Determination of the tritium content in the reactor heavy water; Odredjivanje porasta kolicine tritijuma u reaktorskoj teskoj vodi

    Energy Technology Data Exchange (ETDEWEB)

    Ribnikar, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    Quantity of tritium was measured in the heavy water, in the heavy water vapour and radiolyzed deuterium from the helium cover gas of the RA reactor. It has been shown that isotopic equilibrium D{sub 2}O+DT{r_reversible}DTO+D{sub 2} exists and that it is catalyzed by irradiation. Small quantities of ammonium in the reactor cover gas are inhibiting the migration of tritium from the heavy water. Izmerena ja sadrzina tritijuma u tecnoj teskoj vodi, njenoj pari i radiolizovanom deuterijumu iz helijumske atmosfere reaktora RA. Pokazano je da postoji izotopska ravnoteza D{sub 2}O+DT{r_reversible}DTO+D{sub 2}, koja je katalizovana zracenjem. Male kolicine amonijaka reaktorske atmosfere deluju u smislu otezavanja migracije tritijuma iz teske vode (author)

  3. Possibilities of using metal uranium fuel in heavy water reactors; Mogucnosti upotrebe metalnog urana kao goriva za teskovodne reaktore

    Energy Technology Data Exchange (ETDEWEB)

    Djuric, B; Mihajlovic, A; Drobnjak, Dj [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    There are serious economic reasons for using metal uranium in heavy water reactors, because of its high density, i.e. high conversion factor, and low cost of fuel elements production. Most important disadvantages are swelling at high burnup and corrosion risk. Some design concepts and application of improved uranium obtained by alloying are promising for achievement of satisfactory stability of metal uranium under reactor operation conditions. Postoje ozbiljni ekonomski razlozi za primenu metalnog urana u teskovodnim reaktorima, pre svega zbog njegove velike gustine, odnosno visokog konverzionog faktora, i zbog niskih troskova proizvodnje gorivnih elemenata. Glavne prepreke su bubrenje pri velikim stepenima sagorevanja i opasnost od korozije. Postoje veliki izgledi da se primenom odredjenih projektnih koncepcija i upotrebom legiranjem poboljsanog urana postigne zadovoljavajuca stabilnost metalnog urana u uslovima rada reaktora (author)

  4. Thermal conductivity of the sintered UO{sub 2}; Toplotna provodljivost sinterovanog UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Katanic-Popovic, J; Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1967-04-15

    Phenomena influencing the thermal conductivity of the sintered UO{sub 2} fuel were analyzed. Influence of temperature, density and porosity, additives and irradiation in the reactor core are presented. Thermal conductivity of sintered UO{sub 2} was measured both outside the reactor and during the irradiation in the reactor. Results are discussed and analyzed based on the available literature. Analizirane su pojave koje uticu na toplotnu provodljivost sinterovanog UO{sub 2}, pre svega, sa aspekta njegove primene kao goriva. Izlozen je uticaj temperature, gustine i poroznosti, aditiva i ozracivanja u reaktoru. Na osnovu pregleda dostupne literature kriticki su prikazani rezultati merenja toplotne provodljivosti sinterovanog UO{sub 2} van reaktora i u reaktoru pri ozracivanju (author)

  5. Radiation protection at the RA Reactor in 1995, Part -2, Annex 2, Decontamination and actions, collection of liquid effluents and solid radioactive waste; Deo 2 - Prilog 2 - Dekontaminacija i intervencije, skupljanje tecnih efluenata i cvrstih radioaktivnih otpadnih materijala

    Energy Technology Data Exchange (ETDEWEB)

    Mandic, M; Vukovic, Z; Lazic, S; Plecas, I; Voko, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1995-12-01

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [Serbo-Croat] Tokom rada reaktora RA dolazi do stvaranja odredjenih cvrstih otpadnih materijala cija prosecna kolicina zavisi od vremena rada reaktora i aktivnosti koje se tamo obavljaju. Tokom remonta, kada reaktor ne radi kao i pri akcidentalnim situacijama nastaju vece kolicine otpadnih materijala koje zavise od obima i vrste remontnih operacija i obima dekontaminacije kontaminirane radne povrsine i kontaminiranog alata, predmeta, opreme, itd. Nastali otpadni materijali se razvrstavaju i pakuju na mestu nastanka prema odgovarajucim propisima u skladu sa principima zastite od zracenja i aspekta bezbednosti u cilju minimiziranja nepotrebnog ozracivanja ljudstva za preuzimanje, kontrolu, transport, naknadnu obradu RAO i dekontaminaciju. Pri nerutinskim operacijama (dekontaminacija, remont, kontaminiarni otpadni materijal velike zapremine i sl.), strucna sluzba Institita ZASTITA pruza strucne konsultacije i pomaze pri planiranju

  6. RA Research nuclear reactor - Annual report 1987; Istrazivacki nuklearni reaktor RA - Izvestaj o radu za 1987. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1987, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1987. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3509/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  7. RA Research reactor, Annual report 1988; Istrazivacki nuklearni reaktor RA - Izvestaj za 1988. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1988-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  8. Research nuclear reactor RA - Annual Report 1989; Istrazivacki nuklearni reaktor RA - Izvestaj za 1989. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  9. Research nuclear reactor RA - Annual Report 1990 with the comparative evaluation for the period 1986-1990; Istrazivacki nuklearni reaktor RA - Izvestaj za 1990. godinu uz uporedni pregled za period 1986 - 1990

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1990-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1990, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1990. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  10. Influence of the neutron flux shape on the value of absorbed neutron dose; Uticaj oblika neutronskog spektra na vrednost apsorbovane doze neutrona

    Energy Technology Data Exchange (ETDEWEB)

    Miric, I; Miric, P [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1974-07-01

    This paper deals with the study od specific doses dependence on the type and approximation procedures of neutron spectra. Values of specific dose rates (dose per neutron cm{sub 2}) were analysed for neutron spectra from RB reactor in Vinca, Crac facility in Valduc (France) and HPRR reactor in Oak Ridge (USA). Data used in this analysis were obtained by methods used in Harwell (AERE), Oak Ridge (ORNL), Chalk River (AECL), CEN de Cadarache (CEA) and in the Boris Kidric Institute (IBK). Specific absorbed neutron doses were determined for each of the estimated spectra and presented in the form of kerma/(n.cm{sup -2}) and rad/((n.cm{sup -2}) units. The obtained results have shown the influence of the flux approximation procedure on the values of conversion factors for obtaining neutron doses from neutron flux. U okviru ovog rada radjeno je na ispitivanju zavisnosti specificnih doza od vrste i nacina aproksimacije neutronskog spektra. U radu su analizirane vrednosti specificnih doza (doza po n.cm{sup -2}) za neutronske spektre koji se dobijaju oko sledecih nuklearnih postrojenja: reaktora RB u Vinci, postrojenja CRAC u Valduc-u (Francuska), reaktora HPRR u Oak Ridge-u (SAD). Za analizu su korisceni podaci dobijeni metodama koje se koriste u nuklearnim centrima Harwell (AERE), Oak Ridge-u (ORNL), Chalk River-u (AECL), CEN de Cadarache (CEA) i Institutu Boris Kidric (IBK). Za svaki procenjeni spektar odredjene su specificne apsorbovane doze neutrona izrazene u kerma/(n.cm{sup -2}) i rad/(n.cm{sup -2}) jedinicama. Dobijeni rezultati su pokazali koliko nacin aproksimacije spektra utice na vrednost konverzionih faktora koji sluze za prelazak sa fluksa na dozu neutrona (author)

  11. RA Research reactor, Annual report 1971; Istrazivacki nuklearni reaktor RA - Izvestaj za 1971. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1971-12-15

    effects. In the introduction of this report it has been emphasised that the decision makers should have in mind the negative effects of low budget on the reactor safe and reliable operation. For the sake of reactor, decision about the future operation and financing should be done as soon as possible, either to cease operation or continue with adequate financial support. [Serbo-Croat] Reaktor RA je u 1971. godini radio na nominalnoj snazi 190 dana i 50 dana na manjim snagama. Ukupni rad iznosio je 31606 MWh odnosno 5,3% vise od planiranog, sto je najvisa vrednost od kako je reaktor pusten u rad. Reaktor je koriscen za ozracivanja i eksperimente za 425 korisnika od cega 370 iz Instituta i 55 za korisnika izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. Odstupanja od plana, odnosno veceg ostvarenog rada bilo je u junu i decembru usled posebnih zahteva korisnika. Ukupni broj prekida rada bio je manji od svih prethodnih godina, uglavnom zbog manjeg broja nestanka napona u vreme rada reaktora. U toku godine bilo je samo jedno sigurnosno zaustavljanje, ciji je uzrok bila pojava laznog signala opreme za zastitu reaktora. Nijednog duzeg prekida rada nije bilo zbog neispravnosti opreme. Kracih prekida bilo je usled kidanja spojki na potisnom cevovodu tehnicke vode, sto je bilo izazvano klizanjem zemljista u podrucju crpne stanice na Dunavu. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Nije bilo ni jednog akcidenta niti slucaja koji bi se mogao nazvati akcidentom. Dekontaminirano je znatno manje povrsina nego ranijih godina. Zakljuceno je da je uspesan rad reaktora u 1971. godini rezultat valjanog rada u prethodnim godinama. Medjutim usled jos nedefinisane politike u pogledu buduceg rada, odnosno neizvesnosti u vezi finansiranja, neki poslovi su obustavljeni. Tu spada proucavanje mogucnosti prelaska na koriscenje visokoobogacenog goriva sto bi povecalo korisni neutronski fluks i ucinilo reakor konkurentnim za

  12. Influence of ferrite phase in alite-calcium sulfoaluminate cements

    Science.gov (United States)

    Duvallet, Tristana Yvonne Francoise

    Since the energy crisis in 1970's, research on low energy cements with low CO2- emissions has been increasing. Numerous solutions have been investigated, and the goal of this original research is to create a viable hybrid cement with the components of both Ordinary Portland cement (OPC) and calcium sulfoaluminate cement (CSAC), by forming a material that contains both alite and calcium sulfoaluminate clinker phases. Furthermore, this research focuses on keeping the cost of this material reasonable by reducing aluminum requirements through its substitution with iron. The aim of this work would produce a cement that can use large amounts of red mud, which is a plentiful waste material, in place of bauxite known as an expensive raw material. Modified Bogue equations were established and tested to formulate this novel cement with different amounts of ferrite, from 5% to 45% by weight. This was followed by the production of cement from reagent chemicals, and from industrial by-products as feedstocks (fly ash, red mud and slag). Hydration processes, as well as the mechanical properties, of these clinker compositions were studied, along with the addition of gypsum and the impact of a ferric iron complexing additive triisopropanolamine (TIPA). To summarize this research, the influence of the addition of 5-45% by weight of ferrite phase, was examined with the goal of introducing as much red mud as possible in the process without negatively attenuate the cement properties. Based on this PhD dissertation, the production of high-iron alite-calcium sulfoaluminateferrite cements was proven possible from the two sources of raw materials. The hydration processes and the mechanical properties seemed negatively affected by the addition of ferrite, as this phase was not hydrated entirely, even after 6 months of curing. The usage of TIPA counteracted this decline in strength by improving the ferrite hydration and increasing the optimum amount of gypsum required in each composition

  13. Research nuclear reactor RA - Annual Report 1994; Istrazivacki nuklearni reaktor RA - Izvestaj za 1994. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1994-12-01

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Activities related to improvement of Russian project were continued in 1994. Control and maintenance of the reactor components was done regularly and efficiently. Extensive repair of the secondary coolant loop is almost finished and will be completed in the first part of 1995 according to existing legal procedures and IAEA recommendations. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1994. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i

  14. RA Research reactor, Annual report 1973; Istrazivacki nuklearni reaktor RA - Izvestaj za 1973. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1973-12-15

    podatke o radu i eksperimentima koji su obavljani. U toku godine bilo je 12 sigurnosnih zaustavljanja, od cega 7 zbog zbog elektricnog napona. Od tri zaustavljanja ciji je uzrok bila oprema, dva su bila zbog otkazivanja novih elektronskih cevi. Od dva zaustavljanja koja je izazvalo pogonsko osoblje, jedno je bilo usled nepazljivog ukljucivanja pomocnog potrosaca, a drugo je ucinio operator jer se cinilo da snaga reaktora naglo raste. Kracih prekida rada bilo je tri, usled najavljenog iskljucenja napona. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Nije bilo ni jednog akcidenta. Dekontaminirano je znatno manje povrsina nego ranijih godina, i sakupljeno manje otpada nego prethodnih godina, dok tecnih efluenata nije bilo. Zakljuceno je da uspesan rad reaktora u 1973. godini ima poseban znacaj kada se ima na umu kriza finansiranja izazvana neblagovremenim resavanjem statusa reaktora. Mnogi goruci problemi nisu reseni: kompletiranje rezervnih delova, zamena nekih elemenata opreme, zamena nekih instrumenata, i nabavka visokoobogacenog goriva.

  15. Prenosna peć za pečenje hleba - u funkciji obezbeđenja ishrane pripadnika vojske Srbije u mirovnim misijama/Movable oven for bread baking intended for food preparation in Serbian army peace corps

    Directory of Open Access Journals (Sweden)

    Branko M. Tešanović

    2014-10-01

    Full Text Available Peć za pečenje hleba u poljskim uslovima dodeljuje se jedinicama koje su po svom karakteru relativno stacionarne i kojima po veličini ne bi pripadale pokretne peći. Podesna je za pečenje hleba namenjenog jedinicama koje se nalaze u međunarodnim misijama, u uslovima otežanog snabdevanja, jer navike naših vojnika su da konzumiraju hleb, a ne keks. Peć je montažno-demontažnog tipa, prilagođena za korišćenje na svim vrstama terena. Jednostavne je konstrukcije, što omogućava da se demontira i lako prenosi sa mesta na mesto. / An oven for baking bread in field conditions is assigned to units that are by their nature relatively stationary and whose size does not require a movable bakery. It is intended for baking bread in our units located in international missions with supply difficulties, since our units have a habit od consuming bread instead of biscuits. The oven is of a prefabricated type, adapted for use in all types of terrains, simple design which makes it possible to be, dismantled and easily transported.

  16. Histamine and Antihistamines / Histamin i antihistamini

    Directory of Open Access Journals (Sweden)

    Stojković Nikola

    2015-03-01

    Full Text Available Poslednjih godina beleži se kontinuirani rast prevalencije alergijskih oboljenja. Alergijski imunski odgovor predstavlja jednu kompleksnu mrežu ćelijskih događaja u kojoj učestvuju mnogobrojne imunske ćelije i medijatori. On predstavlja interakciju urođenog i stečenog imunskog odgovora. Ključnu ulogu u imunološkoj kaskadi zauzima histamin, prirodni sastojak tela, koga u alergijskom inflamatornom odgovoru oslobađaju mastociti i bazofili. Cilj ovog rada bio je naglasiti ulogu histamina u alergijskim imunološkim događajima, njegov efekat na Th1 i Th2 subpopulaciju limfocita i produkciju odgovarajućih citokina, kao i ulogu blokatora histamina u tretmanu ovih stanja. Histamin ostvaruje svoj efekat vezivanjem za četiri tipa svojih receptora koji su široko distribuirani u organizmu. Blokatori histamina blokiraju mnogobrojne efekte histamina vezivanjem za ove receptore. Cetirizin, visoko selektivni antihistaminik druge generacije, ne ostvaruje svoje efekte samo vezivanjem za H1 receptore već dovodi do atenuisanja mnogobrojnih zbivanja tokom inflamacijskog procesa. Dobro poznavanje efekata histaminskih blokatora, među njima i cetirizina, može dovesti do pravog odabira terapije u tretmanu alergijskih oboljenja.

  17. Korporatīvā sociālā atbildība.Uzņēmuma ,,Accenture"izpēte

    OpenAIRE

    Skabeiķis, Saulis

    2009-01-01

    Jautājumu par to, vai uzņēmumiem jāuzņemas sociālā atbildība, plaši apsprieda industrializācijas posma sākumā 1880. gadu beigās. Šāda tipa atbildība nozīmē to, ka uzņēmums brīvprātīgi uzņemas pastāvīgas saistības rīkoties ētiski un sekmēt ekonomisko attīstību, vienlaikus uzlabojot darbaspēka, ģimeņu, vietējās un plašāka mēroga sabiedrības dzīves kvalitāti. Mūsdienās šī diskusija sasniegusi to līmeni, kuru saucam par korporatīvo sociālo atbildību. Interese par korporatīvo sociālo atbildību str...

  18. Ventilation system in the RA reactor building - design specifications; Sistem ventilacije u objektu 'RA' - Tehnicki opis

    Energy Technology Data Exchange (ETDEWEB)

    Badrljica, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1984-09-15

    Protective role of the ventilation system of nuclear facilities involve construction of ventilation barriers which prevent release of radioactive particulates or gases, elimination od radioactive particulates and gases from the air which is released from contaminated zones into the reactor environment. Ventilation barriers are created by dividing the building into a number of ventilation zones with different sub pressure compared to the atmospheric pressure. The RA reactor building is divided into four ventilation zones. First zone is the zone of highest risk. It includes reactor core with horizontal experimental channels, underground rooms of the primary coolant system (D{sub 2}O), helium system, hot cells and the space above the the reactor core. Second zone is the reactor hall and the room for irradiated fuel storage. The third zone includes corridors in the basement, ground floor and first floor where the probability of contamination is small. The fourth zone includes the annex where the contamination risk is low. There is no have natural air circulation in the reactor building. Ventilators for air input and outlet maintain the sub pressure in the building (pressure lower than the atmospheric pressure). This prevents release of radioactivity into the atmosphere. Zastitne uloge ventilacionog sistema kod nuklearnih postrojenja obuhvataju formiranje ventilacionih barijera koje onemugucavaju sirenje radioaktivnih cestica ili gasova putem cirkulacije vazduha; eliminaciju radioaktivnih cestica i gasova iz vazduha koji se evakuise iz kontaminiranih prostora u okolinu reaktorskog postrojenja. Formiranje zastitnih ventilacionih barijera ostvaruje se obicno podelom unutrasnjosti objekta na vise ventilacionih zona razlicitih podpritisaka u odnosu na spoljni atmosferski pritisak. Celi prostor zgrade reaktora RA podeljen je u cetiri ventilacione zone. Prva zona je zona najveceg rizika, u koju spadaju reaktorsko jezgro sa horizontalnim eksperimentalnim kanalima, tehnoloske

  19. Technical realization of the VISA-2 Project, contract: 2.01/ I phase, Volume No. I; Tehnicka realizacija projekta VISA-2, ugovor: 2.01/I faza, Album br. I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-12-15

    Cooperation between the Institutes in Vinca and Saclay has started by carrying out the task 'Technical realization of the VISA-2 project' which should enable: obtaining new experimental spaces in the RA reactor with high fast neutron flux for sample irradiation; obtaining experience in reactor continual operation for few months at nominal power of 6.5 MW and increase of RA reactor utilization; solving the problem of activated channels and samples transport, problems of working in hot cells; obtaining irradiated samples for examining radiation effects first in Saclay and later in Vinca. The project is divided in three phases. Phase one covers the reconstruction of the RA reactor fuel channels according to the VISA-2 project demands. The second phase includes the activities related to measuring devices for measuring the temperatures at the incoming and outgoing heavy water in 5 VISA-2 channels, as well as temperature of the samples (55 thermocouples) and testing the channels and capsules after their insertion in the reactor. The third phase includes activities are related to problems of transport of radioactive channels and VISA-2 capsules, problems of cutting as well as packing and transporting of irradiated samples from Vinca to Saclay. This volume includes all the relevant documents for completing the task including contracts, needed preliminary calculations as well as safety analysis. [Serbo-Croat] Saradnja izmedju Instituta u Vinci i Saclay-u zapoceta je realizacijom zadatka 'Tehnicka realizacije projekta VISA-2' koji treba da omoguci: dobijanje novih eksperimentalnih prostora u reaktoru RA sa visokom vrednoscu fluksa brzih neutrona za ozracivanje uzoraka; sticanje pogonskih iskustava u visemesecnom kontilualnom radu na nominalnoj snazi od 6,5 MW i povecanje stepena koriscenja reaktora RA; resenje pitanja transporta aktivnih kanala i uzoraka, problema rada u vrucim celijama; dobijanje ozracenih uzoraka za izucavanje, u prvo vreme u Saclay-u, a kasnije i u Vinci

  20. One procedure for determination of the neutron flux in the nuclear reactor fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bulovic, V; Krtil, J; Maksimovic, Z; Martinc, R [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1979-09-15

    Possibility of determination of the neutron flux in the fuel of a heavy water reactor has been examined. In determination of the flux an iterative procedure was used to compare calculated and measured contents of several fission products. The former contents were determined by calculation of the burning process balance and the latter by non-destructive gamma-spectrometric analysis of fuel. The obtained results prove the possibility of such determination of not only the average value of the flux but also of the change of its intensity during utilization of fuel (author) U radu je ispitivana mogucnost odredjivanja fluksa neutrona u gorivu teskovodnog nuklearnog reaktora. Pri odredjivanju fluksa koriscen je iterativni postupak, u kome se porede izracunati i izmereni sadrzaji nekoliko gama-radioaktivnih fisionih produkata. Prvi sadrzaji su odredjivani preko proracuna bilansa procesa sagorevanja, a drugi - nedestruktivnom gama-spektrometrijskom analizom goriva. Dobijeni rezultati potvrdjuju mogucnost ovakvog odredjivanja ne samo srednje vrednosti fluksa, vec i promene njegovog intenziteta u toku koriscenja goriva (author)

  1. Investigation of corrosion of materials of the irradiation device in the RA reactor; Ispitivanje korozije materijala uredjaja za ozracivanje na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    Zaric, M; Mance, A; Vlajic, M [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Devices for sample irradiation in the vertical RA reactor channels will be made of aluminium alloys. According to the regulations concerned with introducing materials into the RA reactor core, corrosion characterisation of these materials is an obligation. Corrosion properties of four aluminium alloys were investigated both in contact with stainless steel and without it. First part of this report deals with the corrosion testing of aluminium alloys in water by gravimetric and electrochemical methods. Bi-distilled water at temperatures less than 100 deg C was used. Second part is related to aluminium alloys corrosion in carbon dioxide gas under experimental conditions. The second part of research was initiated by the design of the head of the independent CO{sub 2} loop for samples cooling. [Serbo-Croat] Uredjaji za ozracivanje u vertikalnim kanalima reaktora RA, bice napravljeni od legura aluminjuma. Prema propisima o unosenju materijala u RA reaktor materijali se moraju prethodno ispitati i sa stanovista korozije. Ispitivane su korozione pojave na cetiri aluminjumske legure sa i bez kontakta sa nerdjajucim celikom. Prvi deo ovog rada tretira pitanje korozije legura aluminijuma u vodi gravimetrijskim i elektrohemijskim metodama. Koriscena je bidestilovana voda na temperaturi do 100 deg C. Drugi deo se odnosi na ispitivanje ponasanja legura aluminijuma u gasovitom ugljen dioksidu pod uslovima eksperimenta. Drugi deo istrazivanja izvrsen je za potrebe izgradnje glave petlje nezavisnog kola za hladjenje uzoraka gasovitim CO{sub 2}.

  2. RA reactor building and installations; Zgrada 'RA' i instalacije

    Energy Technology Data Exchange (ETDEWEB)

    Badrljica, R; Sanovic, V; Skoric, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-08-15

    RA reactor building is made of reinforced concrete and bricks. It is closed facility with a limited number of controlled openings, doors and windows. The site of the building is 100 m above the sea level, 20 m above the mean Danube level and 8 m above the level of the neighbouring stream Mlaka. The building consists of three parts: central prismatic part, annex - surrounding the central part and the sanitary corridor. The biggest space is the reactor hall. In addition to the detailed description and drawings of the reactor building this documents includes design specifications of: electrical installation, water supply system, sewage system, ventilation and heating, gas and compressed air systems. A separate chapter is devoted to fire protection. Zgrada reaktora RA izgradjena je od armiranog betona i opeke, kao zatvoreni objekat ogranicenog broja kontolisanih otvora, sa ogranicenim brojem vrata i prozora. Plato na kojem je zgrada izgradjena nalazi se na 100 m nadmorske visine, na 20 m iznad srednjeg vodostaja Dunava i 8 m iznad nivoa obliznjeg potoka Mlaka. Zgrada se sastoji iz tri dela: sredisnjeg prizmaticnog dela, aneksa - prstenastog okvira sredisnog dela i sanitarnog propusnika. Pojedinacno najveci prostor zauzima reaktorska hala. Pored detaljnog opisa i plana zgrade, ovaj dokument sadrzi projekat elektricne instalacije, projekat vodovoda i kanalizacije, ventilacije i grejanja, instalacije gasa i komprimovanog vazduha. Posebno poglavlje posveceno je protivpozarnoj zastiti.

  3. RA Research reactor, Annual report 1969; Istrazivacki nuklearni reaktor RA - Izvestaj za 1969. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-12-15

    years of operation as well as purification of heavy water. [Serbo-Croat] Reaktor RA je u 1969. godini radio na nominalnoj snazi 200 dana i 15 dana na manjim snagama. Ukupni rad iznosio je 31131 MWh odnosno 3.77% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimenta prema zahtevima 463 korisnika iz Instituta i 63 izvan Instituta. Ovaj izvestak sadrzi detaljne podatke o snazi na kojoj je reaktor radio tokom 1969. godine i o uradjenim eksperimentima. Zakljuceno je da je reaktor RA uspesno radio prema planu rada. Da nije bilo problema sa napajanjem elektricnom energijom tokom poslednja tri meseca i niskog vodostaja Dunava u septembru i oktobru protekle godine bila bi to najuspesnija godina od pustanja reaktora u pogon. Broj sigurnosnih zaustavljanja nije bio veci u odnosu na prethodne dve godine i pored poteskoca u poslednjem kvartalu. Osoblje je bilo izlozeno povecanim dozama zracenja usled tri incidenta. Jedan je bio raspadanje kenera sa srebrom (zbog duzeg stajanja u aktivnoj zoni), sto je uzrokovalo kontaminaciju radne platforme, tako da je fon porastao za 10 do 100 puta od normalnohg Druga dva slucaja su bila otkazivanje uredjaja za mesanje goriva u tehnoloskim kanalima. Zamena goriva je radjena cetiri puta u toku godine, utroseno je 499 svezih gorivnih elemenata. Primenjena je metoda mesanja svezih gorivnih elemenata sa koriscenim gorivnim elementima u gorivnom kanalu. Dekontaminacija povrsina bila je na nivou prethodnih godina i pored problema sa srebrom. Kako su sa reaktora tokom godine otisla dva saradnika sa visokom spremom broj ljudi je opao na neophodan minimum za pogon i odrzavanje reaktora. Navrsavajuci u ovoj godini deset godina rada moze se reci da su rad i stanje opreme na tehnicki solidnom nivou. Kako bi se posle deset godina rada izvrsila kontrola vaznih komponenti reaktora i obavila rekoncentracija teske vode, za 1970. godinu je planirano da se proizvodnja smanji na 25000 MWh, a baziran je na istim principima kao i planovi za prethodne

  4. Neutron Diffractometer; Neutronski difraktometar

    Energy Technology Data Exchange (ETDEWEB)

    Zivadinovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    RA nuclear reactor is considered as a relatively strong neutron source producing the thermal neutron flux of about 3x10{sup 13} n/cm{sup 2} sec when operating at nominal power of 6.5 MW. Neutron diffraction method is applied in the field of solid state physics, material science, crystallography, magnetism, nuclear physic. Neutron diffractometer at the RA reactor consists of: system for obtaining collimated neutron beam from the horizontal experimental channel neutron monochromator; goniometer and electronic equipment for measurements and collecting the the measurement data. Nuklearni reaktor RA koji pri radu na snazi od 6,5 MW ima fluks termalnih neutrona oko 3x10{sup 13} n/cm{sup 2} sec predstavlja relativno jak izvor neutrona. Tehnika difrakcije neutrona primenjuje se u istrazivanjima fizike crvstog stanja, strukture materijala, kristalografije, magnetizma, nuklearne fizike. Neutronski difraktometar na reaktoru RA sastoji se od sistema za dobijanje kolimisanog snopa neutrona kroz horizontalni kanal reaktora; neutroskog monohromatora; goniometra i elektronskih uredjaja za merenja i registrovanje rezultata. Ovaj izvestaj sadrzi detaljan opis i seme neutronskog difraktometra sa pratecom opremom i elektronskim komponentama.

  5. Dosimetry and radiation shielding at the RA reactor, Annual report 1975, Annex 5; Prilog 5 - Dozimetrija i tehnicka zastita

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    In the working environment at the RA reactor, the level of gamma radiation is measured continuously by the built-in stationary system. According to the needs, measurement are done in the reactor hall every day. The level of gamma radiation is measured separately in typical points when the reactor is operated at nominal power and during intervals between two operating campaigns. The level of neutron radiation is measured according to the needs by means of a mobile spherical neutron detector. These measurements are done in the reactor hall around the horizontal experimental channels. Measured values of neutron radiation are three times lower than the relevant levels of gamma radiation. [Serbo-Croat] Na reaktoru RA vrsi se stalna kontrola nivoa gama zracenja po tehnoloskim i radnim prostorijama, pomocu ugradjenog stacionarnog sistema. Svakodnevno se vrse merenja u reaktorskoj hali, prema ukazanim potrebama. Posebno se mere nivoi gamma zracenja u karakteristicnim tackama pri radu reaktora na nominalnoj snazi i u pauzama izmedju dva kampanje. Merenje nivoa neutronskog zracenja vrsi se diskontinualno pomocu mobilnog sfernog neutronskog dozimetra. Merenja se obavljaju u hali oko horizontalnih eksperimentalnih kanala. Izmerene vrednosti su u proseku tri puta manje od odgovarajucih nivoa gama zracenja.

  6. Nonstationary temperature field in the fuel element; Nestacionarno temperatursko polje u gorivnom elementu

    Energy Technology Data Exchange (ETDEWEB)

    Vehauc, A; Spasojevic, D [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1970-03-15

    Nonstationary temperature field in the fuel element was examined for spatial and time distribution of the specific power generated in the fuel element. Analytical method was developed for calculating the temperature variation in the fuel element of a nuclear reactor for a typical shape of the heat generation function. The method is based on series expansion of the temperature field by self functions and application of Laplace transformation in time coordinate. For numerical calculation of the temperature distribution a computer code was developed based on the proposed method and applied on the ZUSE-Z-23 computer. Razmatrano je nestacionarno temperatursko polje u preseku sipke gorivnog elementa za slucaj prostorne i vremenske raspodele specificne generacije snage u gorivnom elementu. Razradjen je analii postupak odredjivanja promene temperature u gorivu nuklearnog reaktora za tipican oblik funkcije generacije toplote. Postupak se zasniva na razvoju temperaturskog polja po sopstvenim funkcijama i primeni Laplasove transformacije po vremenskoj koordinati. Za efektivno nalazenje temperaturskog polja, postupak je programiran za digitalnu racunsku masinu ZUSE-Z-23 (author)

  7. Analysis of possible accidents on the heavy water system - Annex 4; Prilog 4 - Analiza mogucih akcidenata na sistemu teske vode

    Energy Technology Data Exchange (ETDEWEB)

    Krstic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Analysis of operation of the RA reactor heavy water system has shown that so far there were no failures that could cause reactor shutdown. Consequences of system failures and interruption of heavy water cooling of the core would be very serious. That is the reason for analyzing and estimating these type of failures of system components that could affect the tightness of the system or interrupt its function. The important elements of the heavy water system are: operating cylinder, heavy water pumps, heat exchanger, main and drainage pipes with distribution construction. Failure analysis of all the mentioned system components was done. [Serbo-Croat] Analiza dosadasnjeg rada sistema teske vode na reaktoru RA pokazala je da nije bilo ostecenja i kvarova takvog obima koji bi doveli do prestanka rada reaktora. Posledice ostecenja sistema i prestanak cirkulacije teske vode za potrebe hladjenja jezgra bile bi velike. Zato je potreno analizirati i predvideti takva ostecenja na elementima sistema zbog kojih bi doslo do narusavanja hermeticnosti sistema ili prestanak njegovog rada. Osnovni elementi sitema teske vode su: radni cilindar, pumpe teske vode, izmenjivac toplote, glavni i drenazni cevovodi sa razvodnom armaturom. Uradjena je analiza ostecenja na svim navedenim komponentama sistema.

  8. Annex 5 - Fabrication of U-Al alloy; Prilog 5 - Dobijanje legure U-Al

    Energy Technology Data Exchange (ETDEWEB)

    Drobnjak, Dj; Lazarevic, Dj; Mihajlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Alloy U-Al with low content of aluminium is often used for fabrication of fuel elements because it is stable under moderate neutron flux density. Additionally this type of alloys show much better characteristics than pure uranium under reactor operating conditions (temperature, mechanical load, corrosion effect of water). This report contains the analysis of the phase diagram of U-Al alloy with low content of aluminium, applied procedure for alloying and casting with detailed description of equipment. Characteristics of the obtained alloy are described and conclusions about the experiment and procedure are presented. Sistem U-Al sa niskim sadrzajem aluminijuma jedan je od cesto koriscenih za izradu gorivnih elemenata, jer je dovoljno stabilan pri umerenim gustinama fluksa. Pored toga, u uslovima karakteristicnim za rad nuklearnog reaktora (temperatura, gradijent temperature, mehanicka naprezanja, koroziono dejstvo vode) legure ovog sistema pokazuju daleko bolja svojstva od nelegiranog urana. Referat sadrzi analizu dijagrama stanja U-Al legure sa niskim sadrzajem aluminijuma, primenjeni postupak legiranja i livenja sa opisom pojedinih uredjaja i operacija. Takodje su opisana svojstva dobijene legure i dat je zakljucak o eksperimentu i tehnici rada (author)

  9. Report on environmental control at the 'Boris Kidric' Institute, Vinca, Period 01.01. - 31.12.1979. Annex 3; Izvestaj o radu na kontroli okoline Instituta 'Boris Kidric', Vinca, Period 01.01. - 31.12.1979. god., Prilog 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-10-15

    This report includes description of the regular tasks performed on the territory of the 'Boris Kidric' Institute, namely, radioactivity control of water, precipitation, soil, plants, radioactivity control of aerosols and meteorology measurements. During 1979, total beta activity of aerosols in the air were measured at three measuring stations, two located in the Institute and one about three kilometers far from the Institute in the direction of the predominant wind towards Belgrade. Total of 761 samples were measured. From the obtained results it can be concluded that during the reporting period there was no environmental contamination caused by RA reactor operation. During 1979 the radioactivity of air was significantly lower compared to previous years. [Serbo-Croat] Izvestaj obuhvata prikaz standardnih poslova koji se obavljaju na teritoriji Instituta 'Boris Kidic' u Vinci, i to kontrolu radioaktivnosti voda, padavina, rastinja, zamljista, kontrolu radioaktivnosti aerosola, i meteoroloska merenja. U toku 1979. godine vrsena su merenja ukupne beta aktivnosti aerosola u vazduhu na tri merne stanice, dve u krugu Instituta a jedna na oko 3 km daleko od Instituta u pravcu predominantnog vetra prema Beogradu. Izmeren je 761 uzorak. Na osnovu dobijenih rezultata moze se zakljuciti da u ovom periodu nije bilo kontaminacije okoline usled rada nuklearnog reaktora u Institutu. Tokom 1979. godine doslo je do uocljivog opadanja readioaktivnosti vazduha u odnosu na prethodne godine.

  10. Calorimetric dosimetry of reactor radiation; Kalorimetriska dozimetrija reaktorskog zracenja

    Energy Technology Data Exchange (ETDEWEB)

    Radak, B; Markovic, V; Draganic, I [Institute of Nuclear Sciences Boris Kidric, Odeljenje za radijacionu hemiju, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Calorimetric dosimetry of reactor radiation is relatively new reactor dosimetry method and the number of relevant papers is rather small. Some difficulties in applying standard methods (chemical dosemeters, ionization chambers) exist because of the complexity of radiation. In general application of calorimetric dosemeters for measuring absorbed doses is most precise. In addition to adequate choice of calorimetric bodies there is a possibility of determining the yields of each component of the radiation mixture in the total absorbed dose. This paper contains a short review of the basic calorimetry methods and some results of measurements at the RA reactor in Vinca performed by isothermal calorimeter. Kalorimetrijska dozimetrija reaktorskog zracenja je relativno nova metoda dozimetrije reaktora i broj do sada objavljenih radova je vrlo skroman. S obzirom na slozenu prirodu zracenja postoje neke teskoce pri radu sa standardnim metodama (hemijski dozimetri, jonizacione komere). U principu, upotreba kalorimetra za merenje apsorbovanih doza je najegzaktnija. Osim toga, uz pogodni izbor kalorimetrijskih tela postoji mogucnost za odredjivanje doprinosa pojedinih komponenti smese zracenja u totalnoj apsorbovanoj dozi. U tekstu je dat kratak pregled osnovnih metoda kalorimetrije i neki rezultati merenja sa izotermskim kalorimetrom na reaktoru RA u Vinci.

  11. Irradiation of UO{sub 2}; Ozracivanje UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Stevanovic, M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-10-15

    Based on the review of the available literature concerned with UO{sub 2} irradiation, this paper describes and explains the phenomena initiated by irradiation of the UO{sub 2} fuel in a reactor dependent on the burnup level and temperature. A comprehensive review of UO{sub 2} radiation damage studies is given as a broad research program. This part includes the abilities of our reactor as well as needed elements for such study. The third part includes the defions of the specific power, burnup level and temperature in the center of the fuel element needed for planning and performing the irradiation. Methods for calculating these parameters are includedSerb. Na osnovu pregleda dostupne literature o ozracivanju UO{sub 2} u ovom radu su izlozene i objasnjene pojave koje nastaju pri ozracivanju goriva od UO{sub 2} u reaktoru do razlicitih stepena izgaranja i na razlicitim temperaturama. Pored toga, dat je pregled svih mogucih ispitivanja na radijacionom ostecenju UO{sub 2} u formi sirokog programa istrazivanja. Ovaj deo je dopunjen sudom o mogucnostima naseg reaktora kao i o elementima koji su potrebni za ovakav rad. U trecem delu su izlozeni definicija parametara: specificna snaga, stepen izgaranja i temperatura centra goriva i njihovo izracunavanje za potrebe postavljanja i izvodjenja ozracivanja (author)

  12. Heavy water pumps; Pumpe D{sub 2}O

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Nikolic, M

    1963-12-15

    Continuous increase of radiation intensity was observed on all the elements in the heavy water system during first three years of RA reactor operation. The analysis of heavy water has shown the existence of radioactive cobalt. It was found that cobalt comes from stellite, cobalt based alloy which was used for coating of the heavy water pump discs in order to increase resistance to wearing. Cobalt was removed from the surfaces due to friction, and transferred by heavy water into the reactor where it has been irradiated for 29 876 MWh up to 8-15 Ci/g. Radioactive cobalt contaminated all the surfaces of aluminium and stainless steel parts. This report includes detailed description of heavy water pumps repair, exchange of stellite coated parts, decontamination of the heavy water system, distillation of heavy water. [Serbo-Croat] U toku prve tri godine eksploatacije reaktora RA uocen je neprekidni porast intenziteta zracenja na svim elementima u teskovodnom sistemu. Analizom teske vode utvrdjeno je postojanje radioaktivnog kobalta. Ustanovljeno je da kobalt potice od stelita, legure na bazi kobalta kojim su presvuceni rukavci vratila teskovodnih pumpi radi otpornosi na habanje. Kobalt je trenjem skidan sa povrsina, u toku rada prenosen je teskom vodom u reaktor i ozracivan u toku 29 876 MWh do specificne aktivnosti 8-15 Ci/g. Radioaktivni kobalt je kontaminirao sve povrsine od aluminijuma i nerdjajuceg celika. Ovaj izvestaj sadrzi detaljan opis remonta pumpi, zamene delova teskovodnih pumpi novim delovima bez stelitnog sloja, dekontaminacije teskovodnog sistema, destilacije teske vode.

  13. A pulsed fast reactor; Un reacteur pulse a neutrons rapides; Impul'snyj reaktor na bystrykh nejtronakh; Reactor rapido pulsado

    Energy Technology Data Exchange (ETDEWEB)

    Blokhin, G. E.; Blokhintsev, D. I.; Blyumkina, Yu. A.; Bondarenko, I. I.; Deryagin, B. N.; Zajmovskij, A. S.; Zinov' ev, V. P.; Kazachkovskij, O. D.; Krasnoyarov, N. V.; Lejpunskij, A. I.; Malykh, V. A.; Nazarov, P. M.; Nikolaev, S. K.; Stavisskij, Yu. Ya.; Ukraintsev, F. I.; Frank, I. M.; Shapiro, F. Ji.; Yazvitskij, Yu. S. [Akademiya Nauk, Moscow, SSSR (Russian Federation)

    1962-03-15

    los impulsos de potencia. Asimismo, se efectuaron mediciones del periodo de los neutrones instantaneos, de la fraccion efectiva de neutrones retardados y de los coeficientes de variacion de la reactividad en funcion de la temperatura. (author) [Russian] Impul'snyj reaktor na bystrykh nejtronakh (IBR) rabotaet na nominal'noj moshchnosti v Obedinennom institute yadernykh issledovanij s dekabrya 1960 goda. Reaktor ispol'zuetsya v kachestve impul'snogo istochnika nejtronov dlya fizicheskikh ehksperimentov, provodimykh metodom vremeni proleta. Provodyatsya izmereniya polnogo secheniya, secheniya zakhvata dlya promezhutochnykh nejtronov, issledo- vaniya vzaimodejstviya medlennykh nejtronov s tverdym telom i s zhidkost'yu, izmereniya spektrov nejtronov, ustanavlivayushchikhs ya v. razlichnykh sredakh. V doklade opisany osnovy konstruktsii reaktora i rezul'taty ego issledovanij. Osnovnoj rezhim raboty reaktora-rezhim periodicheskikh impul'sov. Impul'sy moshchnosti voznikayut pri bystrom peremeshchenii podvizhnoj chasti aktivnoj zony reaktora cherez ego nepodvizhnuyu zonu. Podvizhnaya chast' aktivnoj zony zakreplena vo vrashchayushchemsya diske i dvizhetsya so skorost'yu-230 m/sek. Chastota impul'sov moshchnosti mozhet izmenyat'sya s pomoshch'yu vspomogatel'noj podvizhnoj zony v diapazone 2,3-88 im/sek. Srednyaya moshchnost' reaktora - 1 kvt. Polushirina impul'sa moshchnosti - 36 mksek. Reaktor snabzhen sistemoj upravleniya i zashchity, obespechivayushchej avtomaticheskoe podderzhanie srednej moshchnosti reaktora i ego bystruyu ostanovku v sluchae narusheniya rezhima. Reaktor snabzhen sistemoj vakuumirovanny kh nektronovodov, ispol'zuemykh v ehksperimentakh po vremeni proleta. Glavnyj nejtronovod imeet dlinu 1000 m. V protsesse puska i fizicheskikh issledovanij reaktora izuchalos' vliyanie peremeshcheniya organov regulirovaniya i podvizhnykh chastej aktivnoj zony na reaktivnost', izmeryalas' dlitel'nost' impul'sa pri razlichnykh rezhimakh raboty reaktora, izuchalis

  14. Problems of Uranium Monocarbide and Mononitride Technology; Problemes de la technologie des monocarbures et mononitrures d'uranium; Problemy tekhnologii monokarbida i mononitrida urana; Problemas de la tecnologia del monocarburo y del mononitruro de uranio

    Energy Technology Data Exchange (ETDEWEB)

    Yakeshova, L. [Institut Yadernykh Issledovanij Chekhoslovatskoj, Czechoslovak Socialist Republic (Czech Republic)

    1963-11-15

    A critical account of published data is given, and the over-all demands made on ceramic nuclear fuel of the uranium monocarbide and mononitride type are examined. The paper also refers to a number of still unsolved problems, either at the research level or at that of practical application. A short account is given of methods of obtaining monocarbide and preparing compacted products. (author) [French] Le memoire donne un apercu critique de la documentation publiee. Il examine les criteres generaux auxquels doit repondre le combustible nucleaire ceramique du type monocarbure et mononitrure d'uranium. Il indique les problemes qui se posent encore en ce qui concerne les travaux de recherche ou l'utilisation pratique des matieres. Les methodes de preparation des monocarbures et les questions relatives a la fabrication de produits compacts font l'objet d'un bref examen. (author) [Spanish] La memoria examina criticamente los datos publicados. Se exponen los requisitos generales de los combustibles nucleares ceramicos del tipo monocarburo y mononitruio de uranio. Se senalan los problemas aun no resueltos en lo relativo a los trabajos de investigacion o a las aplicaciones practicas de esos materiales. Se describen brevemente los metodos de preparacion de los monocarburos y los problemas que plantean la elaboracion de productos compactos. (author) [Russian] Daetsya kriticheskoe obsuzhdenie literaturnykh dannykh. Razbirayutsya obshchie trebovaniya k keramicheskomu yadernomu toplivu tipa monokarbida i mononitrida urana. Otmechayutsya problemy, kotorye s tochki zreniya issledovatel'skikh rabot ili prakticheskogo primeneniya materialov, ostayutsya eshche ne reshennymi. Kratko obsuzhdayutsya metoda polucheniya monokargida i voprosy prigotovleniya kompaktnykh izdelij. (author)

  15. Strukturna analiza složenih planetarnih prenosnika snage / Structural analysis of compound planetary gear trains

    Directory of Open Access Journals (Sweden)

    Slavko Muždeka

    2005-03-01

    Full Text Available Određivanje osnovnih kinematičkih i dinamičkih karakteristika složenih planetarnih prenosnika je složen proces za koji je razvijeno više analitičkih, grafičkih i grafoanalitičkih metoda. U radu je prikazan način određivanja prenosnog odnosa, opterećenja elemenata i tokova snage za planetarni red sa spoljašnjim i unutrašnjim ozubljenjem preko polužne analogije i primene strukturnog (Wolfovog simbola. Polužna analogija definisana je i za planetarni red sa spoljašnjim ozubljenjem, za koji je, takođe, definisan strukturni simbol. Definisani strukturni simboli iskorišćeni su za definisanje strukture prenosnika tipa Ravigneaux. Primena strukturne šeme za analizu karakteristika složenih planetarnih prenosnika ilustrovana je kroz analizu određenih funkcionalnih stanja planetarnih menjačkih prenosnika. Posebno je definisana mogućnost analize blokiranih stanja planetarnih menjačkih prenosnika. / Determination of basic cinematic and dynamic characteristics of compound planetary gear trains is complex process. Therefore there are many analytical, graphical and graphic-analytical methods. This paper presents method of determination gear ratios, loads and power flows for planetary gear set with the sun and ring gear by lever analogy with the application of Wolfs structural symbol. The lever analogy and structural symbols are also defined for the planetary gear set with two sun gears. Defined structural symbols are employed for definition of Ravigneaux gear structure. Application of structural schemes for an analysis of compound planetary gear trains is illustrated through analysis of certain planetary gearboxes functional state. The possibility of analysis of blocked compound planetary gear train is defined too.

  16. The Use of Copper- 64 in the Investigation of Reaction Mechanisms of Enzymes, Particularly as Related to Food Processing; Emploi de Cuivre-64 dans l'Etude des Mecanismes de Reaction des Enzymes, Notamment en Ce Qui Concerne la Preparation des Denrees Alimentaires; ПРИМЕНЕНИЕ МЕДИ-64 ДЛЯ ИССЛЕДОВАНИЯ МЕХАНИЗМОВ ФЕРМЕНТАТИВНЫХ РЕАКЦИЙ, СВЯЗАННЫХ С ОБРАБОТКОЙ ПИЛИ; Empleo de Cobre-64 en el Estudio de los Mecanismos de Reacciones Enzima Ticas de Interes para la Elaboracion de Alimentos

    Energy Technology Data Exchange (ETDEWEB)

    Arthur, Jr., J. C.; McLemore, T. A. [Southern Regional Research Laboratory, New Orleans, LA (United States)

    1963-03-15

    complejos del tipo Cu-p-quinona. Al afladir el ion a una solucion oxidante despues de iniciada la polimerizacion de los productos de reaccion del tipo o-quinona disminuyo la cantidad de ion cuprico complejado. La memoria examina matematicamente la cinetica del intercambio y de los procesos en virtud de los cuales se forman los complejos del ion cuprico con la enzima, asi como con los productos de reaccion. (author) [Russian] Okislitel'nye fermenty rastitel'nyh tkanej chasto ne aktivny ili lish' slabo aktivny v stadii pokoja, stanovjas' aktivnymi pri povrezhdenii tkanej ili pri otdelenii ot nee. pri obrabotke pishhi jeto privodit k uskoreniju okislenija estestvennyh substratov i polimerizacii produktov, chto menjaet cvet tkani. Katalizatorami jetih reakcij v osnovnom javljajutsja mednye oksidajen. Aktivacija fermenta vedet k ego reakcii inaktivacii. Odnoj ije prichin fenomena reakcii inaktivacii javljaetsja snizhenie jeffektivnoj koncentracii fermentov, vozmozhno, za schet udalenija ili svjazyvanija ego metallosoderzhashhej prosteticheskoj gruppy med'ju. S pomoshh'ju medi-64 in vitro, bylo pokazano, chto v pokojashhemsja rastvore ion dvuhvalentnoj medi mozhet obrazovyvat' kompleksy ili ob- yenivat'sja s med' fermenta, i chto v okisljajushhihsja rast.vorah dobavochnye kolichestva iona dvuhvalentnoj medi mogut obrazovyvat' kompleksy. Kompleksy medno-orto-hinonovogo tipa imejut bolee vysokuju konstantu obrazovanija, chem kompleksy medno-paro-hinonovogo tipa. Kolichestvo komplekse- obrazujushhego iona dvuhvalentnoj medi umen'shalos', esli ion dobavljalsja k okisljajushhemusja rastvoru posle nachala polimerizacii produktov reakcii orto-hinonovogo tipa. Obsuzhdaetsja s matematicheskoj tochki zrenija kinetiki processov obmena i kompleksoobrazovanija dlja ionov dvuhvalentnoj medi s fermentom i produkty reakcii. (author)

  17. O morfematskoj alternaciju talijanskom glagolu

    Directory of Open Access Journals (Sweden)

    Tekavčić Tekavčić

    1972-12-01

    Full Text Available U studiji pod tim naslovom autor razmatra postanak i razvoj tzv. Smjene ili alternacije morfema (tal. alternanza morfematica, engl. morphemic alternance u prezentu talijanskih glagola, od starotalijanskog do suvremenog talijanskog jezika. Dok u starom talijanslmm jeziku opažamo bujnost i koegzistenciju različitih tipova alternacije, suvremeni ju je jezik u velikom broju glagola ukinuo (generalizacijom jednog alomorfa. J edan od bitnih faktora ne samo postanka morfematske alternacije nego i njezina ukidanja jest i analogija, tj. težnja prema predvidivosti ili pretkazivosti glagolskih oblika na osnovu morfematskog sistema. Autor razlikuje tri tipa analogičkih utjecaja: utjecaj jednog člana neke paradigme na druge (intraparadigmatski u., utjecaj odrectenih članova jedne paradigme na članove druge paradigme istoga glagola (interparadigmatski u. i napokon utjecaj određenih oblika jednog glagola na oblike drugog glagola (interverbalni u.. U razvoju prezentskih obliika talijanskog glagola zastupana su sva tri tipa. Za razliku od nekih lingvista, autor razlikuje samo dva tipa morfematske alternacije: automatsku alternaciju, određenu mogućnostima fonematskog sistema i prema torne predvidivu, i leksičku alternaciju, tj. onu koja nije podređena restrikcijama fonematskog sistema i zbog toga nije predvidiva, odnosno predvidiva je samo nakon što prethodno utvrdimo odsječke leksika (u konkretnom slučaju glagole u kojima dolazi. Morfematska alternacija obaju tipova sudjeluje u izraža vanju morfosintaktiičkih opozicija, ali ona nije o njima ovisna u smislu predvidivosti, jer ne dolazi u s vi m glagolima. U glavnom dijelu priloga autor studira najprije one morfematske alternacije koje se osnivaju na alternaoiji vokala (altemanza, vocalica, što je opet posljedica nekih fonematskih procesa (diftongacije vokala /e/, /o/, razvoja diftonga /aw/, zaobljivanje nenaglašenoga fonema /e/ u dodiru s labijalnim konsonantima itd.. Morfematske alternacije

  18. The Role of Exponential and PCTR Experiments at Hanford in the Design of Large Power Reactors; Roles Respectifs des Experiences Exponentielles et du Reacteur d'Etude des Constantes Physiques de Hanford dans les Etudes de Grands Reacteurs de Puissance; Znachenie ehksponentsial'nykh opytov i opytov na reaktore PCTR pri proektirovanii bol'shikh ehnergeticheskikh reaktorov v khehnforde; Papel de los Experimentos Exponenciales y del Reactor PCTR de Hanford en el Proyecto de Grandes Reactores de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Heineman, R. E. [General Electric Company, Richland, WA (United States)

    1964-02-15

    introduccion de cambios en el manejo de los reactores ya existentes, como instrumentos de investigacion en la esfera de la fisica de los reactores y como medio de ensenanza. Compara tambien los capitales invertidos en esas instalaciones y los gastos de explotacion. Describe el perfeccionamiento de nuevas tecnicas experimentales que estas instalaciones permiten aplicar con miras a satisfacer la demanda de nuevos datos experimentales. Es menester tener presentes todos estos datos para poder predecir la evolucion de las necesidades y las tendencias futuras en el empleo de estas instalaciones para los estudios de los reactores de potencia. La memoria describe sucintamente el reactor para el estudio de constantes fisicas e indica la manera en que se piensa utilizarlo en el marco de esa evolucion. (author) [Russian] V Hjen- fordskih laboratorijah v techenie pochti 15 let provodjatsja jeksponencial'nye reaktornye iz- merenija na grafito-uranovyh reshetkah. Hotja rezul'taty jetih opytov ispol'zovalis' dlja opredelenija laplasianov predlagaemyh proizvodjashhih reaktorov, oni takzhe sodejstvovali razvitiju ponimanija fiziki reaktorov jetih sistem. Davno priznano, chto poleznost' kri- ticheskogo opyta ogranichena vvidu ego bol'shogo masshtaba i nedostatochnoj chuvstvitel'nosti v otnoshenii nebol'shih lokalizovannyh narushenij sistemy. Zatem mysl' byla napravlena na sozdanie cel'nogo opytnogo reaktora, v kotorom bylo by svedeno do minimuma kolichest- vo materialov, neobhodimyh dlja poluchenija nuzhnyh dannyh. Jeta popytka privela k postrojke usovershenstvovannoj kriticheskoj ustanovki s neskol'kimi zonami reaktora dlja izmerenija fizicheskih konstant PCTR. Ustanovka ispol'zuetsja dlja okazanija sodejstvija pri razrabot- ke proekta po fizike reaktorov dlja neskol'kih jenergeticheskih reaktorov. Krome togo,re- aktor RSTNjavljaetsja ustanovkoj obshhego naznachenija dlja provedenija izmerenij poperechnyh sechenij na reaktore i dlja opredelenija differencial'nyh i integral'nyh fizicheskih para

  19. Operating Experience with Indian Point Nuclear Electric Generating Station; Experience d'exploitation de la centrale nucleaire d'Indian point; Opyt ehkspluatatsii Indian-pojntskoj yadernoj ehlektrostantsii; Experiencia adquirida con la explotacion de la central nucleoelectrica de Indian point

    Energy Technology Data Exchange (ETDEWEB)

    Beattie, W. C.; Freyberg, R. H. [Consolidated Edison Company of New York, Inc., New York, NY (United States)

    1963-10-15

    potencia, hasta 5 MW(t), a la temperatura ambiente y a temperaturas elevadas, y el 16 de septiembre de ese ano el turbogenerador se conecto por primera vez a la red de la Consolidated Edison. Hasta entrado el mes de noviembre, prosiguieron los ensayos a potencias de hasta 50% del valor teorico, con frecuentes detenciones automaticas, originadas en gran parte por perturbaciones en la seccion ''clasica'' de la central. En cuanto a la seccion nuclear, fueron sobre todo las fallas del mecanismo de mando de las barras de control que contribuyeron a la caida automatica de las barras y a las demoras en la reiniciacion de la marcha despues del paro. El 14 de noviembre de 1962 se detuvo la marcha de la central para proceder a los cambios previstos en las tuberias de la seccion ''clasica'' y para modificar y perfeccionar el mecanismo de mando de las barras de control. Esta ultima operacion comprendia la instalacion de un dispositivo de purga a base de nitrogeno seco para las cajas de los mecanismos de las barras de control, a fin de reducir al minimo los efectos de los escapes de agua, a traves de las juntas. Al parecer, dichas perdidas eran la causa principal de las indicaciones erroneas registradas en el sistema de control del reactor. La central se volvio a poner en servicio el lc de enero de 1963. El 27 de enero de 1963, se dio fin a los ensayos del reactor, con potencias hasta el 100%, en condiciones de carga constante. Los resultados de los ensayos concordaron satisfactoriamente con las previsiones. En la primavera de 1963 se continuaran las pruebas, para estudiar la manera en que el reactor responde a fluctuaciones rapidas de la demanda. (author) [Russian] Blok No. 1 Indian-pojntskoj yadernoj ehlektrostantsii sostoit iz reaktora s vodoj pod davleniem moshchnost'yu 585 mgvt, chetyrekh pervichnykh konturov okhlazhdeniya s gorizontal'nymi teploobmennikami, dvukh rabotayushchikh ka nefti paroperegrevatelej proizvoditel'nost'yu 1 100 tys. funtov/chas i turbogeneratora moshchnost

  20. The Enrico Fermi Atomic Power Plant; La centrais nucleaire Enrico Fermi; Atomnaya ehlektrostantsiya im Ehnriko Fermi.; La central nucleoelectrica Enrico Fermi

    Energy Technology Data Exchange (ETDEWEB)

    Hartwell, R. W. [Power Reactor Development Company, Detroit, MI (United States)

    1963-10-15

    nejtronakh moshchnost'yu 100 mgvt (ehl.) bylo v osnovnom zakoncheno v dekabre 1961 goda. V techenie poslednikh 16 mesyatsev provodilis' shirokie ispytaniya sistem i komponentov. Ehta predpuskovaya programma ispytaniya okazalas' ochen' poleznoj dlya proverki konstruktsii i dlya opredeleniya neobkhodimykh izmenenij. Vse voznikshie problemy okazalis' razreshimymi. V doklade kratko osveshchayutsya naibolee vatnye izmeneniya. Grafitovaya zashchita. V dekabre 1960 goda pervyj kontur byl zapolnen natriem i byli nachaty shirokie ispytaniya. Kogda byl snova otkryt zashchitnyj bak pervogo kontura posle ispytaniya pervogo kontura pri temperature 1000{sup o}F, bylo obnaruzheno, chto bol'shaya chast' grafitovogo bloka zashchity, ustanovlennogo vokrug reaktora, povrezhdena. Vysokotemperaturnye bloki, nasyshchennye borom, uvelichilis' v ob''eme i poteryali prochnost'. Provedennyj tshchatel'nyj analiz pokazal, chto grafitovaya svyaz' povrezhdena. Bylo resheno zamenit' ves' grafit, ispol'zovat' karbid bora v kachestve soedineniya, soderzhashchego bor, ustanovit' blok s pomoshch'yu mekhanicheskogo krepleniya i dovesti vlazhnost' do minimuma. Izmeneniya v korpuse reaktora. Byl proveden remont i vneseny izmeneniya v konstruktsiyu dlya ustraneniya prichiny zaedaniya sborok, dlya likvidatsii povrezhdeniya, kotoroe yavilos' rezul'tatom ehtogo, i dlya ustraneniya v dal'nejshem neispravnosti v peremeshchayushchem mekhanizme upravleniya. Pered remontom byl udalen peremeshchayushchij mekhanizm upravleniya, korpus reaktora byl osushen ot natriya. Posle ehtogo podgotovlennyj peroonvl v spetsial'nykh zashchitnykh kostyumakh byl dopushchen vnutr' korpusa reaktora. Vkhod v rabochuyu zonu obespechivalsya s pomoshch'yu spetsial'nogo- vozdushnogo shl'za, poskol'ku v korpuse reaktora imelsya argon. Izmeneniya parogeneratora. Vo vremya gidrostaticheskikh ispytanij parogeneratora No. 2 byli obnaruzheny techi v neskol'kikh trubkakh. Prichinoj neispravnosti trubok bylo ikh rastreskivanie v rezul'tate korrozii ot

  1. The First Two Years of Operating Experience of the Kahl Nuclear Power Station; Experience acquise pendant les deux premieres annees de fonctionnement de la centrale nucleaire de Kahl; Opyt pervykh dvukh let ehkspluatatsii atomnoj ehlektrostantsii v Kale; Experiencia adquirida en los primeros cuatro anos de funcionamiento de la central nucleoelectrica de Kahl

    Energy Technology Data Exchange (ETDEWEB)

    Bruchner, H. J. [Aeg-Kernenergieanlagen, Frankfurt-am-Main (Germany); Weckesser, A. [Versuchs-Atomkraftwerk Kahl Gmbh, Kahl (Germany)

    1963-10-15

    , une boucle experimentale destinee a l'etude de la surchauffe nucleaire. (author) [Spanish] La central de Kahl constituye la primera central nucleoelectrica europea de propiedad privada, y funciona en carga desde junio de 1961. Esta equipada con un reactor de agua hi que trabaja en ciclo indirecto por circulacion natural. Su capacidad electrica neta asciende a 15 MW y hasta febrero de 1963 habia producido 140 millones de kWh. La memoria revisara la experiencia adquirida durante su funcionamiento, ante todo con el extenso programa de ensayos sobre el comportamiento transitorio y la exploracion gamma. Presentara datos acerca del resultado que han dado en funcionamiento ciertas partes de la central, tales como el dispositivo de accionamiento de las barras de control, el sistema de purificacion de los gases de escape y la turbina. Una vez terminado el programa de ensayos, la planta se exploto en carga basica durante algun tiempo a fin de reunir datos sobre el rendimiento del combustible en la ptactica. Una vez completada esta fase, se instalara en el reactor de Kahl un circuito experimental de sobrecalentamiento nuclear. (author) [Russian] Atomnaya ehlektrostantsiya v Kale, pervaya v Evrope chastnaya atomnaya ehlektrostantsiya, ehkspluatiruetsya pod nagruzkoj s iyunya 1961 goda. Na ehlektrostantsii ustanovlen reaktor s kipyashchej vodoj, kosvennym tsiklom i estestvennoj tsirkulyatsiej. Chistaya ehlektricheskaya moshchnost' reaktora sostavlyaet 15 mgvt. Do fevralya 1963 goda kolichestvo poluchennoj ehnergii sostavilo 140 mln. kvt.ch. Rassmotren opyt ehkspluatatsii, v chastnosti rasshirennaya programma ispytanij: naprimer,povedenie reaktora pri perekhodnom protsesse i kontrol' gamma-izlucheniya. Budut predstavleny rezul'taty izucheniya ehkspluatatsionnoj kharakteristiki nekotorykh komponentov ustanovki, naprimer sistemy privoda reguliruptsikh sterzhnej, sistemy udaleniya gaza i turbiny. Posle osushchestvleniya ehtoj programmy ispytanij ustanovka v techenie nekotorogo vremeni

  2. Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Kozomara-Maic, S; Cupac, S; Raickovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1982-12-15

    During 1982 the Ra reactor was operated at 2 MW power with the initial core configuration with 80% enriched fuel. The reactor power would be limited until the ventilation system is be repaired and the emergency cooling system built. The limited operation regime during 1982 had twofold application: as regular regime for the users according to their demands and for experiments related to the testing operation at 2 MW power level. The following reactor physics activities were affected by this operational regime: methods for regular operation control (determining power density and burnup distribution, reactivity variation, et,); measurement of utilization parameters (spatial distribution of the neutron flux); analysis of origin and consequences of irregularities during operation (control of heavy water and gas composition by gamma spectrometry, control of fission products, control of the heavy water purification system); safety analyses including future new systems (emergency cooling and ventilation) [Serbo-Croat] Reaktor RA je tokom 1982 godine radio sa pocetnom konfiguracijom jezgra sa 80% obogacenim gorivom na snazi od 2 Mw. Snaga je ogranicena dok se ne izvrsi rekonstrukcija sistema ventilacije i ugradnja sistema za udesno hladjenje. Rezim rada na ogranicenoj snazi koriscen je u 1982. godini dvojako: kao normalni radni rezim za potrebe korisnika i za eksperimenta u okviru probnog rada na snazi 2 MW. Ovim rezimom rada uslovljene su delatnosti u okviru reaktorske fizike na sledece oblasti: metodologija kontrole redovnog radnog rezim (odredjivanje raspodele snage i izgaranja goriva, promene reaktivnosti, itd.), merenje eksploatacionih parametara reaktora (prostorna raspodela neutronskog fluks, i sl,), analiza uzroka i posledica pojava neregularnosti u radu fizickim metodama (kontrola sadrzaja teske vode i gasa gama spektometrijom, kontrola fisionih produkata, kontrola sistema za preciscavanje teske vode), sigurnosne analize ukljucujuci buducu izgradnju novih sistema

  3. Annual report for 1979, Results of environmental radioactivity control on the 'B. Kidric' Institute site - precipitations, dust deposition, soil, plants, river sludge (Danube), Annex 2; Godisnji izvestaj za 1979. godinu, Rezultati rada na poslovima kontrole radioaktivnosti zivotne sredine na teritoriji Instituta 'B.Kidric' Deo: padavine i natalozena prasina, vode, zemljiste, rastinje, recni mulj (Dunav), Prilog 2

    Energy Technology Data Exchange (ETDEWEB)

    Ajdacic, N; Martic, M; Vujovic, V; Janicijevic, Z; Jovanovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-10-15

    As previously, the control of the environmental radioactivity on the Institute site, was done by measuring the total beta activity of the following samples: precipitation, fallout deposits; water, soil, plants, and water and sediments from the Danube river at 1145 km. The regular control included 1706 samples. In addition to the regular control of the environment of the nuclear facility a number of water and heavy water samples were analyzed related to the repair and renewal actions at the RA reactor. Results of these analyses (total beta activity, electric conductivity and gamma spectrometry) were submitted in separate reports. Upon demand of the dosimetry service responsible for the control of the working environment of Radioisotope Laboratory 070, six samples (surface contamination, plants and soil) were taken from the area behind the HL building where radioactive waste is kept. Total beta activity of these samples has shown significant contamination of the soil and plants. Director and the decontamination service of the radiation protection laboratory were informed immediately about these results so that adequate measures could be undertaken. [Serbo-Croat] Kontrola radioaktivnosti zivotne sredine na teritoriji IBK, kao i prethodnih godina, vrsena je merenjem totalne beta radioaktivnosti uzoraka: padavina i natalozene prasine, voda, zemljista, rastinja i uzoraka vode i sedimenata uzimanih sa 1145 km reke Dunav. U okviru redovne kontrole sakupljeno je 1706 uzoraka. Pored redovne kontrole radioaktivnosti okoline nuklearnog postrojenja obradjeno je i mereno vise uzoraka voda, kao i teske vode (u vezi sa remontom reaktora RA), Rezultati ovih analiza (totalna beta aktivnost, elekticna provodljivost i gama specrometrijska analiza) podneti su u vidu posebnih izvestaja. Na zahtev dozimetrijske sluzbe odgovorne za kontrolu radne sredine u OOUR-070, odredjena je totalna beta aktivnost sest uzoraka briseva, rastinja i zemljista u cilju ustanovljavanja kontaminacije

  4. Determination of D{sub 2}O-2% Enriched Uranium Lattice Parameters by Means of a Critical System; Determination des Parametres d'un Reseau Uranium Enrichi a 2%-Eau Lourde au Moyen d'un Ensemble Critique; Opredelenie s pomoshch'yu kriticheskoj sistemy parametrov reshetki s 2%-nym obog ashcheniem Urana i s zamedlitelem D{sub 2}O; Determinacion, Mediante un Conjunto Critico, de los Parametros de un Reticulado de D{sub 2}O y Uranio Enriquecido al 2%

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N.; Takac, S.; Markovic, H.; Bosevski, T. [Boris Kidric Institute of Nuclear Sciences, Belgrade, Yugoslavia (Serbia)

    1964-02-15

    las tecnicas utilizadas en las mediciones. Los datos experimentales sirvieron a continuacion para deducir los parametros del reticulado, dennidos por la formula de cuatro factores y el estudio matematico del cuerpo del reactor con arreglo a la teoria de difusion de dos grupos. Los resultados obtenidos se comparan con los valores corrientemente asignados a los mismos parametros para configuraciones de reticulados medidos. Se presentan las desviaciones halladas en el valor de n y en la integral de resonancia para el {sup 238}U. En conclusion, se analiza la utilidad y precision de los datos obtenidos con los experimentos criticos para la construccion y explotacion de un reactor de investigacion de D{sub 2}O y uranio enriquecido. (author) [Russian] Daetsja opisanie serii opytov, vypolnennyh s cel'ju opredelenija osnovnyh parametrov reshetki s 2%-nym obogashheniem urana i s zamedlitelem v vide D{sub 2}O. Toplivnye jelementy predstavljali soboj polye cilindry, pokrytye aljuminiem i smochennye kak snaruzhi, tak i iznutri vodoj. Opyty provodilis' na kriticheskoj sborke RB Instituta jadernyh nauk im. Boris Kidric v Belgrade. Udobooptekaemaja geometricheskaja forma jetoj sistemy daet vozmozhnost' sravnitel'no prosto teoreticheski ob'jasnit' rezul'taty opytov i provesti neposredstvennoe gotovoe sravnenie s raschetami dvuhgruppovoj teorii diffuzii. Izmerenija, vypolnennye dlja desjati razlichnyh konfiguracij reshetki, vkljuchali opredelenie laplasiana, kojefficienta reaktivnosti urovnja vody i blok-jeffekta dlja potoka teplovyh i nadteplovyh nejtronov vnutri kamery reaktora. Opisyvaetsja metodika ctih izmerenij. Dannye opytov ispol'zujutsja dlja vyvedenija parametrov reshetki, opredeljaemyh po formule chetyreh somnozhitelej i pri primenenii k aktivnoj zone reaktora dvuhgruppovoj teorii diffuzii. Rezul'taty sravnivajutsja so standartnymi raschetami teh zhe parametrov dlja izmerjaemyh konfiguracij reshetki. Otmechajutsja otklonenija v velichine p i rezonansnogo integrala U-238. V

  5. A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Allday, C. [United Kingdom Atomic Energy Authority, Risley, Warrington, Lancs (United Kingdom)

    1963-10-15

    enriquecido tambien se puede utilizar como combustible oxido de uranio natural enriquecido con plutonio. En la memoria se resume la experiencia adquirida en la produccion de combustible de oxido para el AGR y en la explotacion del reactor y los planes para la regeneracion del combustible. Se examina la posibilidad de utilizar combustible de plutonio y se analizan las consecuencias que tendria su adopcion sobre los costos y el ciclo del combustible. Por ultimo, se destaca la importancia de los reactores Magnox y AGR en el programa energetico del Reino Unido. (author) [Russian] a ) Prirodnyj uran/topdivnyj tsikl ''Magnoks''. Soedinennoe Kor olevstvo izb ralo reaktor na prirodnom urane s grafitovym zam edli tel em i gazovy m okhlazhdeniem v kachestve osnovy programmy po yadernoj ehnergii. Ono ehkspluatirovalo ehti reaktory v Kolder-Kholle i Chepelkrosse v techenie semi det; reaktory v Berkli i Braduehlle v nastoyashchee vremya nakhodyatsya v stadii ehkspluatatsii, a reaktory v semi drugikh mestakh v stadii stroitel'stva ili planirovaniya. Toplivo dlya ehtikh reaktorov proizvoditsya na zavode v Springfilde i zatem perevozitsya dlya zagruzki k mestopolozheniyu reaktora. Posle oblucheniya i razgruzki toplivo transportiruetsya na zavod v Uindskejl dlya otdeleniya urana i plutoniya ot produktov deleniya. Daetsya opisanie opyta CK v oblasti konstruktsii i proizvodstva toplivnykh ehlementov, ehkspluatatsii reaktora, transportirovki obluchennogo topliva i posleduyushchej obrabotki topliva. Upominaetsya o povedenii topliva v reaktore i ob al'ternativnykh programmakh zagruzki l razgruzki toplivnykh ehlementov; ehta tema razrabatyvaetsya v drugikh trudakh. b) Reaktory, ispol'zuyushchie obogashchennoe toplivo. Soedinennoe Korolevstvo razrabatyvaet usovershenstvovannyj reaktors gazovym okhlazhdeniem AGE, prototip kotorogo voshel v stroj v 1963 godu. Toplivo proizvoditsya iz obogashchennoj okisi urana, zaklyuchennoj v obolochku iz nerzhaveyushchej stali, i Sudet pererabatyvat'sya posredstvom

  6. Fuel location, homogeneity and amount in flat and tubular configurations; Repartition, Homogeneite et Quantite du Combustible dans les Elements a Configuration Plate ou Tubulaire; Polozhenie, gomogennost' i kolichestvo topliva v ploskikh i trubchatykh konfiguratsiyakh; Disposicion, Homogeneidad y Cantidad de Combustibles en Configuraciones Planas y Tubulares

    Energy Technology Data Exchange (ETDEWEB)

    Meester, P. de [Studiecentrum voor Kernenergie, Mol (Belgium)

    1965-10-15

    a presion (PWR) en funcionamiento, y por otra parte, garantizar una carga de combustible suficiente y uniformemente distribuida. Como verificacion visual, puede usarse la radiografia. En cambio, si se necesita un analisis cuantitativo conviene emplear un espectrometro de centelleo gamma que mida la radiacion emitida por el {sup 235}U. Se analizan en la memoria los resultados obtenidos con unas 400 placas de combustible y con una primera partida de tubos. Este metodo permite controlar las caracteristicas de Conformacion y los casquetes. Las mediciones de absorcion con una fuente radiactiva no dieron resultados tan satisfactorios. Se analizan en la memoria resultados numericos de mediciones estaticas y de registros continuos. La cantidad absoluta de combustible en cada zona debe conocerse para poder realizar los calculos relativos al funcionamiento del reactor y tambien debe conocerse la cantidad de combustible contenida en casa elemento completo, para poder llevar el control de las existencias de combustible y poder comparar con la evaluacion del grado de combustion realizada despues de la irradiacion. Se considera en la memoria la elaboracion y el uso de distintos elementos patrones. Se analizan el grado de exactitud y la eliminacion de errores. Se proponen algunas mejoras que podrian introducirse en los ensayos,. (author) [Russian] Teplovydelyayushchie ehlementy dlya materialovedcheskogo reaktora BR-2 mozhno montirovat' libo s plastinkami, poluchennymi v rezul'tate protsessa kadro- voj ramki, libo s trubkami, poluchennymi s pomoshch'yu odnovremennogo prodavlivaniya. V pro- tsesse izgotovleniya i do zagruzki reaktora neobkhodimo proverit' ili izmerit' raspolo- zhenie, gomogennost' i absolyutnoe kolichestvo topliva. Raspolozhenie topliva dolzhno byt' izvestno dlya pomeshcheniya serdechnika v plastinakh i trubkakh i dlya pervoj otsenki kachestva produkta v otnoshenii geometricheskikh spetsifikatsij. S pomoshch'yu tuliya-170 byli proizvedeny radiografiya priblizitel

  7. Carducci i tradicionalni pesniški jezik

    Directory of Open Access Journals (Sweden)

    Ivan Klajn

    1972-12-01

    Full Text Available Giosue Carducci je jedini veliki pesnik iz perioda kada je italijanska poezija napuštala tradicionalni jezik, iskovan još u vreme Petrarke, i postepeno ga zamenjivala živim govornim jezikom svoga doba. Otuda je važno utvrditi koliki udeo u Carduccijevom jeziku imaju nasledjeni poetski arhaizmi. Pregled tekstova pokazuje da je C. najkonzervativniji u morfologiji, gde uveliko upotrebljava, na primer, stare oblike ličnih zamenica, enklitičke zamenice posle glagola u indikativu i proklitičke ispred imperativa, zastarele nastavke u prezentu glagola I konjugacije, imperfektu II i III konjugacije, 3. licu jednine i množine preterita, kondicionalu itd kao i arhaične oblike glagola essere, fare, andare i drugih. Manje takvih pojava ima u fonetici, gde se ne mogu uvek jasno razlikovati arhaizmi od toskanizama. Red reči je u osnovi linearan i blizak proznom stilu, mada u mladalačkim pesmama ima još dosta tradicionalnih inverzija i inada se neke od njih sreću i kasnije. Za rečnik je karakteristično da C. za država takoreći sve stare poetske izraze, ali im u kasnijem periodu svog stvaralaštva priključuje i savremene reči, tako da paralelno upotrebljava npr. augello i uccello, nube i nuvola, pargolo i bambino i sl. Latinizmi imaju dvostruku vrednost, pošto su neki od njih preuzeti od italijanskih klasika, dok su drugi inovacije onog tipa koji će doći još do mnogo većeg izražaja u delu D'Annunzija. Opšti zaključak je da kod Carduccija tradicionalni jezik čini osnovu, na koju se, naročito na leksičkom polju, nadoveznju elementi proznog i govornog jezika, ali (za razliku od Pascolija i drugih novijih pesnika stari oblici se ne odbacuju i nema svesne želje za modernizacijom.

  8. New Phase in the System Uranium-Molybdenum-Silicon; Nouvelle phase dans le systeme uranium-molybdene-silicium; Novaya faza v sisteme uran-molibden'-kremnij; Una fase nueva en el sistema uranio-molibdeno-silicio

    Energy Technology Data Exchange (ETDEWEB)

    Sikirica, M.; Ban, Z. [Rudjer Bokovic Institute, Zagreb, Yugoslavia (Croatia)

    1963-11-15

    }Si{sub 3}. Opredelenie struktury osnovano isklyuchitel'no na poroshkovykh dannykh, pokazavshikh, chto ehta novaya faza prinadlezhit k geksagonal'noj sisteme. Vyyavlena prostranstvennaya gruppa P6/mmc ili odna iz podgrupp. Razmery ehlementarnoj yachejki najdeny ravnymi a - 5,37{sub 0} A; s s 8,58{sub 2} A. Sravnenie raschetnykh i nablyudaemykh intensivnostej ukazyvaet na bol'shoe skhodstvo so strukturoj faz Lavesa tipa C 14. (author)

  9. Crucible-Free Synthesis of Silicides and Borides; Synthese de siliciures et de borures sans creuset; Bestigel'nyj sintez silitsidov i boridov; Sintesis de siliciuros y boruros sin crisol

    Energy Technology Data Exchange (ETDEWEB)

    Ban, Z.; Sikirica, M. [Rudjer Boskovic Institute, Zagreb, Yugoslavia (Croatia)

    1963-11-15

    rasplavlennogo kremniya. Ehtu zonu poluchali, putem bombardirovki ehlektronami. Sintez boridov analogichen, no reaktsii v osnovnom yavlyayutsya reaktsiyami tipa tverdoe-tverdoe. Nachal'nyj nagrev reaktsionnoj smesi osushchestvlyali pri pomoshchi puchka ehlektronov, a dal'nejshij nagrev proizvodili ehlektronami, rasseyannymi na ionizirovannykh gazoobraznykh produktakh reaktsii. (author)

  10. Primjena spektrometrijskih metoda u analizi metalurških uzoraka

    Directory of Open Access Journals (Sweden)

    Anita Štrkalj

    2016-07-01

    Full Text Available Instrumentalne metode analize nezamjenjive su u znanstvenim istraživanjima, a sve više i u praksi gdje se zahtijeva što brže dobivanje rezultata, kao i što veća točnost. U metalurškoj praksi već se dulji niz godina primjenjuju spektrometrijske metode analize i to najčešće optička emisijska spektrometrija s izravnim očitanjem. Međutim koncentracija pojedinih legirnih elemenata u suvremenim metalnim materijalima vrlo je niska, često niža od granice detekcije optičkih emisijskih spektrometara s izravnim očitanjem. U ovom radu određivana je koncentracija bora u nodularnom lijevu primjenom optičke emisijske spektrometrije s izravnim očitanjem (OES, optičke emisijske spektrometrije s induktivno spregnutom plazmom (ICP-OES te atomske apsorpcijske spektrometrije s grafitnom tehnikom (AAS-GF. Dobiveni rezultati pokazali su da se optička emisijska spektrometrija s izravnim očitanjem i optička emisijska spektrometrija s induktivno spregnutom plazmom mogu primijeniti za određivanje bora u ispitivanim uzorcima (tablica 1. Ako se zahtijeva vrlo točna analiza, a posebno ako se radi o vrlo niskim koncentracijama, optička emisijska spektrometrija s induktivno spregnutom plazmom pogodnija je metoda, uz uvjet da su uzorci pravilno pripremljeni. Atomska apsorpcijska spektrometrija s grafitnom tehnikom nije pogodna za određivanje bora u uzorcima ovog tipa. Tijekom provođenja analize dodatna pažnja usmjerena je na eliminaciju negativnog utjecaja grafitne kivete na rezultat analize. Osim toga, u radu je praćen utjecaj načina otapanja uzoraka na rezultate analize bora spomenutim metodama. Rezultati su pokazali da pažljiva priprema uzoraka u zatvorenom sustavu pridonosi točnijem rezultatu analize.

  11. Candida albicans bucais de crianças com síndrome de Down: comportamento de tubos germinativos, exoenzimas e sensibilidade a toxinas"killer" = Buccal candida albicans of children with down’s syndrome: behavior of germ tubes, exoenzimes and sensibility to killer toxins

    Directory of Open Access Journals (Sweden)

    Ribeiro, Evandro Leão

    2007-01-01

    Full Text Available Baseado na necessidade de melhor compreensão dos mecanismos de colonização e patogenicidade por leveduras de Candida provenientes da cavidade bucal de crianças com Síndrome de Down, o objetivo deste estudo de caso controle foi avaliar a capacidade de produção de tubos germinativos e exoenzimas (aspartil proteinases e fosfolipases por C. albicans bucais e o comportamento frente a toxinas “killer”. Foram empregadas 35 (87,5% cepas de C. albicans bucais de crianças com Síndrome de Down e 10 (12,5% de crianças sem síndrome. A produção de tubos germinativos e a detecção de exoenzimas e sensibilidade a toxinas por isolados de Candida foram realizadas segundo as técnicas de Reynolds-Braude, Ruchel, Prince e Polonelli et al. respectivamente. O teste de Reynolds-Braude mostrou melhor capacidade indutora de formação de tubos germinativos no grupo de crianças com Síndrome de Down. Em ambos grupos teste e controle houve a detecção de exoenzimas, entretanto cepas de C. albicans de crianças com alteração cromossômica apresentaram-se mais aspartil proteolíticas e fosfolipidolítipas. Diferenças estatísticas foram significativas em relação ambas capacidades biológicas anteriormente descritas (teste de Reynolds-Braude e atividade exoenzimática das cepas de Candida (p < 0,05. Biotipagem por toxinas “killer” mostrou maior diversidade de biotipos em crianças com síndrome de Down. Conclui-se que as cepas de C. albicans oriundas da mucosa bucal de crianças com Síndrome de Down apresentaram in vitro uma maior predisposição a colonização e a patogenicidade, além de uma melhor expressividade fenotípica em relação às toxinas “killer”

  12. Reactor Radiation Loops as Large Gamma Sources; Boucles d'irradiation des reacteurs nucleaires utilisees comme sources gamma intenses; Radiatsionnye kontury yadernykh reaktorov kak moshchnye gamma-istochniki; Empleo de circuitos de irradiacion de los reactores como fuentes gamma de gran intensidad

    Energy Technology Data Exchange (ETDEWEB)

    Ryabukhina, Yu. S.

    1963-11-15

    vybrany kontury na zhidkikh pri komnatnoj temperature splavakh indiya. Bylo izucheno povedenie dvukh ehvtekticheskikh splavov indiya po otnosheniyu k nekotorym konstruktivnym materialam, i v nachale 1960 g. byl zapushchen pervyj stendovyj indij-gallievyj kontur. V rezul'tate dal'nejshikh rabot byli zapushcheny model'nyj indij-galdievyj kontur s aktivnost'yu v obluchatele do {approx} 100 g. eh k v radiya pri reaktore IRT AN Gruzinskoj SSR i stendovyj indij-gallij-olovyannyj kontur v kanale reaktora IRT IAEH AN SSSR. Nakonets, v 1962 g. byl zapushen rabochij indij-gallij-olovyannyj kontur pri reaktore IRT AN Latvijskoj SSR dlya provedeniya polupromyshlennykh radiatsionnykh protsessov. Maksimal'naya aktivnost' obluchatelya kontura 30 000 g. eh k v radiya. Doklad sostoit iz 4 razdelov: 1. Raschety radiatsionnykh konturov. Obobshchaetsya prodelannaya rabota po metodam rascheta radiatsionnykh konturov. 2. Model' radiatsionnogo indij-gallievogo kontura reaktora IRT-2000 v Tbilisi. Opisyvaetsya dejstvuyushchij kontur. 3. Indij-gallij-olovyannyj radiatsionnyj kontur yadernogo reaktora IRT AN Latvijskoj SSR. Opisyvaetsya dejstvuyushchij kontur. 4. Perspektivy dal'nejshego razvitiya radiatsionnykh konturov. Opisyvayutsya ehksperimenty, skhemy i privodyatsya raschety, na osnovanii kotorykh predstavlyaetsya vozmozhnym sozdanie konturov na tverdom margantse i mobil'nykh konturov na zhidkikh splavakh indiya. (author)

  13. Non-Destructive Testing Methods Applied to Multi-Finned SAP Tubing for Nuclear-Fuel Elements; Essais Non Destructifs de Gaines a Ailettes, en Poudre d'Aluminium Frittee, pour Elements Combustibles; Nedestruktivnye metody ispytaniya rebristykh trub iz spechennogo alyuminikiog'o poroshka dlya yadernykh toplivnykh ehlementov; Metodos de Ensayo No Destructivo Aplicados a Tubos de SAP con Aletas Multiples Destinados a Elementos Combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Lund, S. A. [Danish Central Welding Institution, Copenhagen (Denmark); Knudsen, P. [Danish Atomic Energy Commission, Research Establishment, Risoe (Denmark)

    1965-09-15

    corrientes de Foucault. (author) [Russian] Komissija po atomnoj jenergii Danii predprinjala izuchenie jenergeticheskogo reaktora s organicheskim teplonositelem i tjazhelovodnym zamedlitelem. Toplivnym jelementom dlja reaktora javljaetsja puchok iz 19 sterzhnej; toplivnyj sterzhen' soderzhit spechennye tabletki iz dvuokisi urana v dvuhmetrovoj trube iz spechennogo aljuminievogo poroshka. Truby dolzhny byt' ochen' horoshego kachestva, chtoby obespechit' optimal'nye uslovija perenosa tepla i sohranenija celostnosti toplivnyh jelementov vo vremja jekspluatacii reaktora. Dva primera otnositel'no konstrukcii trub svidetel'stvujut ob ochen' nebol'shih razmernyh dopuskah. Dlja obespechenija sootvetstvujushhego kachestva trub razrabotan strogij kontrol' v znachitel'noj stepeni osnovannyj na nedestruktivnyh metodah. Privoditsja opisanie jetih metodov, razrabotannyh dlja izmerenija tolshhiny stenok i diametrov i dlja obnaruzhenija defektov. Slozhnoe poperechnoe sechenie 24-rebernoj truby ne pozvoljaet primenjat' ul'trazvukovye metody ili metody vihrevyh tokov dlja izmerenija tolshhiny stenok. Pojetomu razrabotan special'nyj kontrol'no-izmeritel'nyj pribor, registrirujushhij beta-izluchenie, osnovannyj na principe oslablenija beta-izluchenija, poluchaemogo ot istochnika stroncija-90, pomeshhennogo vnutri truby. Metod ul'trazvukovogo rezonansa pri pogruzhenii primenjaetsja dlja postojannoj registracii tolshhiny stenok bolee prostyh konstrukcij 12-rebernyh trub. Vnutrennij i vneshnij (mezhdu granjami reber) diametry postojanno registrirujutsja bystrodejstvujushhimi sistemami vozduhomerov. Defekty obnaruzhivajut s pomoshh'ju ul'trazvuka metodom impul's-jeho i metodom vihrevyh tokov. Metodom ul'trazvuka mozhno legko obnaruzhivat' poperechnye no ne prodol'nye treshhiny. Pojetomu, krome proverki ul'trazvukom, primenjaetsja ispytanie vihrevymi tokami. (author)

  14. Use of Synthetic Polymers in Nuclear Emulsions for Fast-Neutron Dosimetry; Primenenie sinteticheskikh polimerov v yadernykh ehmul'siyakh dlya dozimetrii bystrykh nejtronov

    Energy Technology Data Exchange (ETDEWEB)

    Bradna, F. [Laboratorija Radiologicheskoj Dozimetrii Instituta Jadernykh Issledovanij CHSAN Praga, CSSR (Czech Republic)

    1967-01-15

    -acetate substrate 190-{mu}m thick, which was an effective proton radiator. The emulsions were irradiated with fast neutrons of fluence 1.56 x 10{sup 8} n/cm{sup 2} from an RaD-Be source. For increased efficiency of neutron detection, supplementary proton radiators such as polyvinyl alcohol (PVA), tri-acetate (T) and polyethylene (PE) of the optimum thickness were used during irradiation of the emulsion. Dosimetric analysis of the results gave the following: (1) The efficiency of detection was increased, in comparison with normal gelatin emulsions, by: (a) up to 25% when using polymers No. 1 and No. 2, depending on the degree of filling, and (b) 100% when polymer No. 1 was used in a hydrogen-saturated emulsion taken as a standard polymer-gelatin emulsion (SPGE), (2) When the optimum supplementary proton radiators (PVA, T, PE) were added to this SPGE, its detection efficiency was further increased to 330%. (author) [Russian] V dannoj rabote predlagajutsja rezul'taty ispytanij svojstv v Laboratorii radiologicheskoj dozimetrii IJaI ChSAN vodorodom obogashhennyh jadernyh jemul'sij, prednaznachennyh dlja registracii bystryh nejtronov i privoditsja sravnenie dozimetricheskih harakteristik jetih jemul'sij novogo tipa s harakteristikami do sih por ispol'zuemyh zhelatinovyh jemul'sij. Iz serii v laboratorii sintezirovannyh polimerov naibolee interesnymi okazalis': 1) olivinil'acetal' 2,4-disul'fokisloty benzaldegida (polimer N2 1); 2) sopolimer a-acetilaminoakrilovoj kisloty i N-vinilpirrolidona (polimer No 2). Otdel'no izuchalas' vozmozhnost' primenenija rastvorov polivinilovogo spirta s bolee vysokim soderzhaniem vodoroda po sravneniju s vysheukazannymi ispytannymi polimerami (No 1, No 2) dlja propityvanija polimero-zhelatinovyh jemul'sij i dlja prigotovlenija iz nego plenok v kachestve radiatora protonov. Polimery N21 i N9 2 primenjalis' predvaritel'no v ispytatel'noj ammiachnoj jemul'sii. Bylo ustanovleno, chto polimer No 1 ne okazyvaet zametnogo vlijanija na fotohimicheskie svojstva

  15. Void Reactivity Effects in the Second Charge of the Halden Boiling Water Reactor; Effets Cavitaires dans la Deuxieme Charge du Reacteur a Eau Lourde Bouillante de Halden (HBWR); Ehffekty pustotnoj reaktivnosti vo vtoroj zag HBWR; Effectos de Cavitacion en la Segunda Carga del Reactor de Agua Pesada Hirviente de Halden (HBWR)

    Energy Technology Data Exchange (ETDEWEB)

    Lunde, J. E. [OECD Halden Reactor Project (Norway)

    1964-02-15

    temperaturas elevadas. La concordancia es menos satisfactoria para valores intermedios del volumen relativo de los vacios. El efecto de reactividad se calcula macroscopicamente mediante una teoria de las perturbaciones. (author) [Russian] Jeffekt reaktivnosti pustot, vyzvannyh kipeniem v kanalah dlja teplonositelja vo vtoroj zagruzke Haldejskogo kipjashhego tjazhelovodnogo reaktora (HBWR) byl izmeren kak v jeksperimentah nulevoj moshhnosti s imitaciej pustot, tak i v uslovijah fakticheskoj moshhnosti. Jeksperimenty s imitirovannymi pustotami sostojali v izmerenii jeffekta reaktivnosti pustotnyh kolonn, vvodimyh v tonkostennye trubki na razlichnuju glubinu. Trubki byli ustanovleny v raznyh polozhenijah mezhdu prodol'nymi rebrami v odinochnoj sborke, sostojashhej iz semi sterzhnej, prakticheski identichnoj normal'nym toplivnym jelementam vtoroj zagruzki. Jetot jeksperiment pozvolil izuchit' zavisimost' reaktivnosti ot pustogo ob{sup e}ma, a takzhe zavisimost' reaktivnosti ot polozhenija puzyr'kov para v kanale dlja teplonositelja. Jeksperiment byl vypolnen na norvezhskoj ustanovke nulevoj moshhnosti NORA s aktivnoj zonoj iz 36 jelementov vtoroj zagruzki i s geometriej reshetki, analogichnoj geometrii reshetki reaktora HBWR. Temperaturnaja zavisimost' pustotnogo jeffekta byla izuchena na jeksperimental'noj ustanovke nulevoj moshhnosti, imevshej aktivnuju zonu Iz 100 toplivnyh jelementov reaktora HBWR. V odinochnom toplivnom jelemente uroven' vody v kanale dlja teplonositelja snizhalsja do razlichnyh glubin i vlijanie na reaktivnost' jetogo otklonenija ot normal'nyh uslovij izmerjalos' pri razlichnyh temperaturah a intervale temperatur 50 -220eS. Vlijanie pustotnoj reaktivnosti na moshhnost' bylo izmereno na reaktore HBWR kak funkcija jadernoj jenergii pri razlichnyh temperaturah zamedlitelja v diapazone 150 -230e S pri moshhnostjah do 16mgvt (pri samoj vysokoj temperature). Kojefficient pustotnoj reaktivnosti na moshhnosti javljaetsja vazhnym pokazatelem pri opredelenij

  16. Forecasting the Quantity and Activity of Fission Products in France in Future Years in the Light of Atomic Energy Development; Quantite et Activite des Produits de Fission Obtenus en France dans les Annees a Venir Compte Tenu du Developpement de l'Energie Atomique; 041a 041e 041b 0414 ; Cantidad y Actividad de los Productos de Fision que se Obtendran en Francia en los Anos Venideros, Habida Cuenta del Desarrollo de la Energia Atomica

    Energy Technology Data Exchange (ETDEWEB)

    Guirlet, J.; Lavie, J. M. [Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    en un momento dado, asi como la actividad de los productos de fision para un periodo determinado. (author) [Russian] Pri pomoshhi formuly Vignera-Uoja teoreticheski vozmozhno predusmotret' aktivnost' slozhnoj smesi produktov raspada ljubogo reaktora. Issledovanija provodilis' s uchetom vozmozhnogo razvitija atomnoj jenergetiki vo Francii do 1975 goda. Predpolagalos', chto uran v reaktore budet nahodit'sja tri ili shest' mesjacev. Takzhe vozmozhno ustanovit' aktivnost' opredelennogo produkta raspada i opredelit' ego radioaktivnyj raspad. Pri issledovanijah dlja trehmesjachnoj aktivacii byl vybran stroncij. Kazhdyj kompleks grafikov daet obshhuju aktivnost' dlja ljubogo perioda, a takzhe, sobstvennuju aktivnost' produktov raspada, sootvetstvujushhuju opredelennomu periodu. (author)

  17. Concluding Remarks; Zaklyuchitel'noe slovo

    Energy Technology Data Exchange (ETDEWEB)

    Budker, G. I. [Institute of Nuclear Physics, Siberian Department of the USSR Academy of Sciences, Novosibirsk, Union Of Soviet Socialist Republics (Russian Federation)

    1969-01-15

    I feel that the changes which have taken place in science in the last few years open up new possibilities, about which I should like to say a few words. In 1951 we began work on thermonuclear reactions in the confident belief that we would solve the problem with a rush and immediately. I was assigned the task of ensuring that our future thermonuclear reactor would not get too much out of hand. It was like the story of the man who wished to invent a perpetual motion machine and had taken out a patent on a method for keeping it under control. This attitude stemmed from the successes in developing ''explosive thermonuclear reactors'', a task which was achieved within a very short period of time, leaving physicists with the impression that they could do everything - and do it fast. However, experience soon showed that here we had a scientific rather than a technological problem and that it would be necessary to study in detail the physics of plasmas - which we have now been doing for over ten years. [Russian] Mne kazhetsja, chto za poslednie gody- v nauke proizoshli izmenenija, otkryvshie novye vozmozhnosti, na kotoryh ja hotel by ostanovit'sja. Ja hochu napomnit', chto v 1951 godu my nachali raboty po fizike plazmy i termojadernym reakcijam. U nas byla uverennost', chto my reshim jetu problemu s hodu, srazu. Mne bylo porucheno obespechivat' regulirovanie budushhego termojadernogo reaktora, chtoby tot ne ochen' ''razognalsja'' i ne vyshel iz-pod kontrolja. Sejchas jeto poruchenie napominaet istoriju o tom, kak odin hotel izobresti vechnyj dvigatel' i vzjal patent na to, chtoby tot ne razgonjalsja do beskonechnyh skorostej. . . Bol'shie uspehi v razrabotke ''vzryvchatyh termojadernyh reaktorov'', kotorye byli sozdany za ochen' korotkoe vremja, porodili u fizikov uverennost' v to, chto oni mogut sdelat' vse i sdelat' bystro. Odnako ochen' skoro zhizn' pokazala, chto jetim delom nuzhno zanimat'sja ne kak konstruirovaniem, a kak naukoj, chto nado razvivat' plazmennuju

  18. Production of radioisotopes at the Boris Kidric Institute of Nuclear Sciences at Vinca, Yugoslavia; Proizvodnja radioaktivnih izotopa

    Energy Technology Data Exchange (ETDEWEB)

    Teofilovski, C [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    The investigations in order to master the production of radioisotopes were commenced simultaneously with the beginning of RA nuclear reactor construction at Vinca, in 1956. A new organization division - Laboratory for chemistry of high activity accepting beside other problems also the programme for mastering the regular production of radioactive material was formed in 1959. Various problems during the realization of this programme have been solved, starting with the staff training for work with radioactive material on the high level activity (to 7500 Ci/source), construction and equipment of the laboratory area for safe work, up to development of the whole series of chemical-technological procedures and techniques for regular production of various radioactive products, as well as the methods for their chemical, radiometric and pharmaceutical control. Owing to the successful realization of this programme, the Institute 'Boris Kidric' supplies to-day regularly 110 organizations in the country with various radioactive products, applied in medicine, industry and research. The annual product of the radioactive solutions of radioisotopes J-131, Au-198, P-32, S-35 etc., amounts to about 75 Ci, radiographic sources Ir-192 and Co-60 to 2000 Ci and Co-60 sources for teletherapy and the other applications to many thousand curies (author) [Serbo-Croat] Paralelno sa pocetkom izgradnje nuklearnog reaktora RA u Vinci 1956. godine zapoceta su istrazivanja u oblasti osvajanja proizvodnje radioizotopa. 1958. god. formirana je nova organizaciona jedinica - Laboratorija za hemiju visoke aktivnosti, koja je, pored ostalog, prihvatila i program osvajanja redovne proizvodnje radioaktivnog materijala. U toku realizacije programa reseni su raznovrsni problemi pocev od pripreme kadrova za rad sa radioaktivnim materijalom na visokom nivou aktivnosti (do 7500 Ci/izvor), izgradnje i opremanja laboratorijskog prostora za bezbedan rad, do razvoja citavog niza hemijsko-tehnoloskih postupaka i

  19. Description of Radiation Sources Installed at the French Atomic Energy Commissariat; Description de sources de rayonnement installees au commissariat a l'energie atomique; Opisanie istochnikov oblucheniya, nakhodyashchikhsya v frantsuzskom komissariate po atomnoj ehnergii; Descripcion de las fuentes de radiaciones instaladas en el commissariat a l'energie

    Energy Technology Data Exchange (ETDEWEB)

    Leveque, P

    1960-07-15

    organicas, ya que el flujo epitermico y rapido provoca la activacion de la mayor parte de los productos sometidos a la irradiacion. A continuacion, el autor describe las instalaciones del Centro de Aplicaciones Atomicas de Lyon creado en las proximidades de dicha ciudad por un grupo de industriales. Este Centro, que segun esta previsto comenzara a funcionar en 1960, tendra un caracter semi-industrial (para comenzar, una fuente de cobalto-60 de 3 000 curies y mas adelante, otra de 40 000 curies) y permitira realizar operaciones de irradiacion de una manera continua. (author) [Russian] Prezhde vsego avtor daet opisanie chetyrekh ustanovok, nakhodyashchikhsya v yadernom issledovatel'skom tsentre v Sakleh. - Laboratornyj istochnik v 600 kyuri kobal'ta-60; ispol'zuemyj pribor yavlyaetsya prostym i bezopasnym, no ne daet vozmozhnosti izmenyat' potok gamma-luchej. - Pribor, sostoyashchij iz semi istochnikov kobal'ta-60 (samyj moshchnyj v 1000 kyuri), ustanovlennykh v betonnoj kamere; pnevmaticheski j pribor pozvolyaet ustanovit' odin ili neskol'ko neobkhodimykh istochnikov v rabochem polozhenii. - Kamera vmeshchaet 100 sterzhnej yadernogo goryuchego ot novogo reaktora EL3; chast' ehtoj kamery prisposoblena dlya okhlazhdeniya, chto pozvolit proizvodit' opyty nad konservatsiej pishchevykh produktov dejstviem oblucheniya. - Vertikal'nye kanaly reaktora EL 2, tak nazyvaemye ''okna khimika''; kogda ehti kanaly obernuty kadmievoj fol'goj, dostigaemyj potok gamma-luchej perekhodit so 100000 na 200000 rentgeno/chasov, no oni mogut sluzhit' tol'ko dlya oblucheniya organicheskikh materialov, tak kak imeetsya aktivatsiya bol'shej chasti obluchaemykh produktov pri pomoshchi bystrogo ehpitermicheskogo potoka. Zatem avtor daet opisanie pribora, ustanovlennogo v Lionskom tsentre po ispol'zovaniyu atomov, postroennogo okolo Liona gruppoj promyshlennikov. EHtot pribor, pusk v ehkspluatatsiyu kotorogo predusmotren na nachalo 1960 goda, budet nosit' polupromyshlennyj kharakter (istochnik kobal'ta-60

  20. The Electric Field in an MHD Duct with Permeable Electrodes when the Hall Effect is Present in the Flow of the Moving Medium; 042d 041b 0414

    Energy Technology Data Exchange (ETDEWEB)

    Emec, Ju. P.; Panasevich, L. L. [Institut Elektrodinamiki AN USSR, Kiev, USSR (Ukraine)

    1968-11-15

    raspredelenie toka v okrestnosti provodjashhih stenok kanala. Putem vybora zakona vduva (otsosa) jelektroprovodnoj sredy-podavljajutsja koncevye javlenija na jelektrodah (obuslovlennye jeffektom Holla dvizhushhegosja potoka i geometriej kanala) i raspredelenie toka na nem vyravnivaetsja . Vyvodjatsja neobhodimye i dostatochnye uslovija, pri kotoryh plotnost' toka prinimaet ogranichennye znachenija vblizi oboih koncov pronicaemogo jelektroda. Zakon raspredelenija skorosti na provodjashhej stenke pri jetom, kak pravilo, znakoperemennyj: na otdel'nyh uchastkah jelektroda neobhodimo proizvodit' vduv, a na drugih - otsos provodjashhej sredy. Drugoe obstojatel'stvo, kotoroe projavljaetsja blagodarja pronicaemym jelektrodam, svjazano s integral'nymi harakteristikami MGD-preobrazovatelej. Tak, pri anizotropii provodimosti (obuslovlennoj jeffektom Holla) v linejnom magnitogidrodinamicheskom kanale s dvumja pronicaemymi jelektrodami v sluchae, kogda cherez odin jelektrod vduvaetsja, a cherez vtoroj otsasyvaetsja jelektroprovodnaja sreda, sovmeshheny svojstva hollovskogo i faradeevskogo preobrazovatelej jenergii. Jeta shema techenija izuchaetsja v dannoj rabote. Matematicheski nahozhdenie jelektricheskogo polja privodit k resheniju neodnorodnoj kraevoj zadachi Rimana-Gil'- berta s razryvnymi kojefficientami. Jeta zadacha reduciruetsja k kraevoj zadache Rimana (v sluchae polosy v klasse-avtomorfnyh funkcij) i ee reshenie, opirajushheesja na svojstva integralov tipa Koshi, polucheno v zamknutoj forme. (author)

  1. Sail-Type Wind Turbine for Autonomous Power Supplay: Possible Use in Latvia

    Science.gov (United States)

    Sakipova, S.; Jakovics, A.

    2014-12-01

    Under the conditions of continuous increase in the energy consumption, sharply rising prices of basic energy products (gas, oil, coal), deterioration of environment, etc., it is of vital importance to develop methods and techniques for heat and power generation from renewables. The paper considers the possibility to use a sail-type wind turbine for autonomous power supply in Latvia, taking into account its climatic conditions. The authors discuss the problems of developing a turbine of the type that would operate efficiently at low winds, being primarily designed to supply power to small buildings and farms distant from centralized electricity networks. The authors consider aerodynamic characteristics of such a turbine and the dependence of the thrust moment of its pilot model on the airflow rate at different angles of attack. The pilot model with a changeable blade shape has been tested and shows a good performance. Darbs veltīts vienam no atjaunojamo enerģiju veidiem - vēja enerģijai, analizētas tās izmantošanas iespējas. Vispirms īsi raksturota vēja enerģijas izmantošana pasaulē, kā arī vērtētas izmantošanas perspektīvas no inženiertehniskā un klimatisko apstākļu viedokļa. Turpinājumā raksturota situācija Latvijā, t. sk., arī vēja potenciāla pieejamība dažādos reģionos, kā arī vēja enerģijas izmantošanas efektivitāti raksturojošie lielumi. Konstatējot problēmu, rast vēja turbīnu risinājumus Latvijas apstākļiem ar maziem vidējiem vēja ātrumiem, izveidots buras tipa turbīnas modelis. Šī modeļa raksturlielumu izpēte veikta vēja tunelī Karagandas universitātē, konstatējot relatīvi labus efektivitātes rādītājus tiešai un pretējai vēja plūsmai. Izmantojot mērījumu rezultātus, ierosināti sistēmas uzlabojumi, kurus plānots pētīt turpmāk. Šādas sistēmas potenciāli var rast lietojumu tur, kur nepieciešami autonomi enerģijas avoti.

  2. Influence of the Previous History of the Raw Material on Sintering of UO{sub 2}; Influence des antecedents de la matiere premiere sur le frittage de UO{sub 2}; Vliyanie obrabotki iskhodnogo veshchestva na spekanie UO{sub 2}; Influencia de la historia previa de la materia prima sobre la sinterizacion del UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Aparicio, E.; Alonso, J. A.; Pedregal, J. D. [Junta de Energia Nuclear Madrid (Spain)

    1963-11-15

    medio de prefijar las caracteristicas granulometricas de la materia prima, sino la molienda y clasificacion de los polvos. Las uranias ensayadas en este trabajo son materiales convencionales representantes de tipos diferentes de fabricacion por el origen y metodo operatorio. Del estudio de las pastillas obtenidas se deducen las posibilidades y limitaciones de cada tipo de urania en el proceso adoptado. Se controlan las caracteristicas de superficie especifica, granulometria, analisis termico diferencial y termogravimetricoy estequiometria de los polvos, asi como la densidad, contraccion, estructura y estequiometria de las pastillas. (author) [Russian] Izlagayutsya ehksperimental'nye dannye, na kotorykh osnovan primenyaemyj odnim zavodom metod izgotovleniya tabletok UO{sub 2}. Soglasno ehtomu metodu granulometricheskaya kharakteristika iskhodnogo veshchestva opredelyaetsya zaranee ne putem upravlyaemogo osazhdeniya, a razmel'cheniem i sortirovkoj poroshka. V dannoj rabote ispol'zovalis' obraztsy obychnoj okisi urana, otlichayushchiesya po sposobu izgotovleniya i po proiskhozhdeniyu. Issledovanie privelo k nekotorym vyvodam otnositel'no vozmozhnostej i ogranichenij metoda v zavisimosti ot tipa ispol'zuemoj okisi urana. Privodyatsya rezul'taty izmereniya udel'noj poverkhnosti, granulometrii, termicheskikh differentsial'nogo i termogravimetricheskogo analizov i stekhiometrii poroshkov, a takzhe po plotnosti usadki, strukture i stekhiometrii tabletok. (author)

  3. Diagnosis by Liver Scintigraphy; Gepatoskennograficheskaya semiotika

    Energy Technology Data Exchange (ETDEWEB)

    Zubovskij, G. [Nauchno-Issledovatel Skij Rentgeno-Radiologicheskij Institut M3 RSfSR, Moskva, SSSR (Russian Federation)

    1969-05-15

    principles of liver scintigraphy makes it possible to improve the diagnostic efficacy of the scanning process for various liver diseases. (author) [Russian] Gepatoskennografija stala odnim iz vazhnyh metodov diagnostiki' zabolevanij pecheni. ' Chashhe vsego jetot metod ispol'zuetsja s cel'ju obnaruzhenija ochagov destrukcii. Obsledovano 2000 bol'nyh. U 1200 - sostojanie pecheni mozhno bylo schitat' dostoverno ustanovlennym, iz nih: u 335 - na osnovanii revizii, v processe operacii, u 180 -na osnovanii punkcionnoj biopsii, u 55-na osnovanii autopsii, u ostal'nyh - putem kliniko-laboratornyh issledovanij i dlitel'nogo nabljudenija. 102 bol'nym, narjadu so skennirovaniem, byli provedeny takzhe kontrastnye rentgenologicheskie issledovanija sosudov pecheni. U 500 bol'nyh predpolagalis' ochagovye porazhenija pecheni (luchevye fibrozy pecheni, kisti i opuholi), u ostal'nyh 700 - diffuznye (cirrozy, gepatity, sistemnye zabolevanija krovi i dr.). Analiz skennogramm u J200 bol'nyh s dostoverno ustanovlennym sostojaniem pecheni daet osnovanie razrabotat' kriterii gepatosken.nograficheskoj semiotiki, po tipu ispol'zuemyh v rentgenodiagnosticheskoj praktike. K takim kriterijam otnosjatsja izmenenija topografii, formy, razmerov pecheni,. sravnitel'noj kontrastnosti ee izobrazhenija, a takzhe vyjavlenie selezenki i zhelchnogo puzyrja. Bylo ustanovleno, chto, v zavisimosti ot tipa patologicheskogo processa i ego rasprostranjonija, obnaruzhivajutsja ves'ma harakternye priznaki izmenenija gepatoskenno-graficheskoj kartiny, uchet kotoryh pozvoljaet bolee pravil'no delat' zakljuchenie ne tol'ko o lokalizacii processa, no i o ego prirode. Opredeleny takzhe izmenenija gepatoskenno- graficheskoj kartiny, nabljudaemye pri zabolevanijah okruzhajushhih pechen' organov, naprimer, legkih, diafragmy, podzheludochnoj zhelezy. Na osnovanii detal'nogo analiza88 skennogramm obsledovannyh bez priznakov porazhenija pecheni razrabotany ponjatija normal'nogo, skennograficheskogo izobrazhenija pecheni, v

  4. Ateities įžvalgos kaip e. valdžios plėtros strateginio planavimo sudedamoji dalis: siūlomas įžvalgų tyrimo proceso modelis

    Directory of Open Access Journals (Sweden)

    Rokas Grincevičius

    2013-01-01

    žvalgų metodika paremtų projektų skaičiumi (Keenan M., Popper R., 2008, todėl atsiranda šios srities informacijos tuštuma. Nedidelę jos dalį bandoma užpildyti šiuo straipsniu. Raktažodžiai – ateities įžvalgos, e. valdžia, strateginis planavimas, prognozavimo metodikos. Tyrimo tipas – požiūrio pristatymas.

  5. Multi-Objective Optimization of Transmission Lines / Elektropārvades Līnijas Daudzkriteriālā Optimizācija

    Science.gov (United States)

    Berjozkina, S.; Sauhats, A.; Neimane, V.

    2013-10-01

    Introduction of new advanced electrical connections into a transmission grid reduces the capacity of existing overhead lines (OHLs). At the same time, designing & building of new OHLs and substations involves considerable technical, environmental and economical problems. The authors propose a concept of the multi-objective optimization for selection of transmission line routes, towers (their type, placement and geometry), of conductors, insulators, dampers, earthing and lightning protection systems, span lengths, etc.. The optimization is organized in five stages. At the first and second stages a search for optimum solutions is performed along with determination of the main impacting factors. The next two stages present a two-objective optimization based on Pareto's approach. At the last stage (exemplified by a case study), the probability of the restriction removal conditions is assessed, and preventive measures are identified. The presented approach uses a real line design and is intended for minimizing the total invested capital and maximizing the net present value. In the framework of this approach 20 alternatives have been elaborated, which can successfully be applied in the cases described in the paper. Elektropārvades tīklam rodas nepieciešamība pēc jauniem elektriskajiem pieslēgumiem, kas noved pie esošo gaisvadu līniju jaudas nepietiekamības. Viens no iespējamajiem pastāvošās problēmas risinājumiem ir jaunu gaisvadu līniju un apakšstacijas būvniecība. Gaisvadu līniju projektēšana ir saistīta ar ievērojamām tehniskām, vides un ekonomiskām problēmām. Darbā aprakstīta elektropārvades līnijas optimālās trases izvēles daudzkritēriju optimizācijas koncepcija, ieskaitot balstu tipa, balstu izvietojuma koordināšu, balstu ģeometrijas, vadu tipu un parametru, izolatoru tipu, vibroslāpētāju tipu, zibensaizsardzības un zemēšanas sistēmu, kā arī laidumu garumu izvēles optimizāciju. Optimizācijas uzdevums tiek organiz

  6. High-voltage-powered transistorized preamplifier; Pre-amplificateur transistorise avec alimentation haute tension; Vysokovol'tnyj ehnergeticheskij predvaritel'nyj usilitel' na tranzistorakh; Preamplificador transistorizado alimentado con alta tension

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Jr, W E; Wakefield, A W [University of Washington, Seattle, WA (United States)

    1962-04-15

    perekhodom p-n-p uvelichilo edinichnyj tolchok napryazheniya v dinamicheskom diapazone ot 1 millivol'ta do 5 vol't. Stabilizatsiya rabochego napryazheniya dlya skhemy ehmitternogo vykhoda obespechivaetsya nebol'shim zenerovskim diodom. Potreblenie toka tipichnym distantsionnym stsintillyatsionnym detektorom, v kotorom primenena dannaya skhema, kolebletsya ot 0,35 do 0,65 milliamper, v to vremya, kak vysokoe napryazhenie, podavaemoe na stsintillyatsionnyj detektor, izmenyaetsya ot 800 do 1500 vol't. Pribor obsluzhivaet 500 futov koaksial'noj linii v 52 oma s poterej 25-protsentov amplitudy impul'sa; on ispol'zovalsya s distantsionnymi detektorami stsintillyatsionnogo tipa i s nejtronnymi detektorami tipa BF{sub 3} s otlichnymi rezul'tatami. (author)

  7. Improved Oxidation Resistance of Zirconium Resulting from Addition of Small Amounts of Copper; Amelioration de la Resistance a l'Oxydation du Zirconium par de Faibles Additions de Cuivre; Povyshenie soprotivlyaemosti k okisleniyu tsirkoniya posle dobavlenij nebol'shikh kolichestv medi; Aumento de la Resistencia del Circonio a la Oxidacion por Agregado de Pequenas Cantidades de Cobre

    Energy Technology Data Exchange (ETDEWEB)

    Loriers, H.; Darras, R.; Baque, P. [Centre d' Etudes Nucleaires de Saclay (France)

    1966-02-15

    chastnosti splav s 2,5% medi, vidimo, predstavljajut interes v kachestve materialov dlja pokrytija ili konstrukcionnyh materialov dlja toplivnyh jelementov reaktorov tipa tjazhe- laja voda - uglekislyj gaz. Korrozija cirkonija, vyzyvaemaja uglekislym gazom, svoditsja po sushhestvu k okisleniju, v techenie kotorogo voznikajut dva processa: 1) sozdanie monoklinicheskogo cirkonievogo sloja, cherez kotoryj kislorod rasseivaetsja putem migracii anionnyh ''dyrok''; 2) rastvorenie i diffuzija kisloroda, kotoryj protekaet putem ego vvedenija v metall. Sochetanie gravimetricheskih dannyh i izmerenij plotnostej sloev okisi pozvoljaet opredelit' dva sootvetstvujushhih kojefficienta diffuzii. Jetot raschet po analogii raspro- stranjaetsja na sluchaj s dvojnymi, medno-cirkonievymi splavami pri koncentracii medi nizhe ili ravnoj 4 ves%. Sravnenie poluchennyh rezul'tatov pokazyvaet, chto kojefficient diffu- zii kisloroda v obrazovavshemsja sloe okisi umen'shaetsja s uvelicheniem kolichestva medi v rassmatrivaemom splave; s drugoj storony, sootvetstvujushhij kojefficient diffuzii kislo- roda v splave, esli on neskol'ko izmenen pri 600 Degree-Sign S, umen'shaetsja pri 700 Degree-Sign S s uvelicheniem kolichestva medi do 2,5%. Povyshenie soprotivljaemosti k okisleniju, svjazannoe s zamedle- niem processov diffuzii, dostigaetsja, v chastnosti, v rezul'tate prodolzhitel'nogo sohrane- nija kinetiki parabolicheskogo tipa, v to vremja kak v sluchae s nesoedinennym cirkoniem ili s drugimi splavami rastreskivanie sloja okisi v rezul'tate otslaivanija bystro privodit k linejnoj kinetike okislenija. (author)

  8. Transmutation doping and recoil effects in semiconductors exposed to thermal neutrons; Transmutations provoquees et effets de recul dans les semi-conducteurs exposes aux neutrons thermiques; Prisadka i sdacha v rezul'tate prevrashcheniya poluprovodnikov pod dejstviem teplovykh nejtronov; Impurificacion por transmutacion y efectos de retroceso en los semiconductores expuestos a neutrones termicos

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, Jr, J H; Cleland, J W [Solid State Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-01-15

    ,2, 39 chasov. Poehtomu okolo 3 aktseptorov (Ca{sup 71}) vvodyatsya na kazhdyj donor (As{sup 75} i Se{sup 77}), i putem vybora prodolzhitel'nosti oblucheniya mozhno sokratit' kontsentratsiyu ehlektronov Se tipa ''n'' do ves'ma malykh znachenij ili prevratit' Se tipa ''n'' v tip ''p''. Period poluraspada, vedushchij k obrazovaniyu Ga71, dostatochno prodolzhitelen, tak chto podrobnaya ''radioaktivnaya titratsiya'' mozhet soprovozhdat'sya opredeleniem koehffitsienta KHolla i ehlektroprovodnosti. Opyty pokazyvayut takzhe, chto priblizitel'no odin ehlektron na kazhdyj zakhvat nejtrona udalyaetsya defektom reshetki, sozdannym otdachej yadra pri zakhvate ispuskaemykh gamma-luchej. EHti vytesnennye atomy mogut byt' vozvrashcheny obratno na svoe mesto v normal'noj reshetke putem otzhiga pri 450 Degree-Sign C. Byli proizvedeny takzhe nablyudeniya nad dejstviem otdachi v kremnie, prichem bylo ustanovleno, chto na kazhdyj zakhvat ustranyaetsya priblizitel'no 2 nositelya zaryada. Posledstviya ehtikh rezul'tatov, a takzhe rezul'taty v otnoshenii germaniya obsuzhdayutsya v funktsii ot zakhvata spektra gamma-luchej. V sur'myanistom indii zakhvat gamma-luchej iz In{sup 115} nedostatochen dlya togo, chtoby vytesnit' bol'shoe chislo yader, tak chto glavnym vozdejstviem yavlyaetsya obrazovanie Sn{sup 116}, kotoryj stanovitsya donorom pri zamene mesta v reshetke indiya. YAdernaya prisadka predstavlyaetsya perspektivnoj dlya izucheniya mnogochislennykh slozhnykh poluprovodnikov, vvedenie v kotorye primesej khimicheskim sposobom predstavlyaetsya zatrudnitel'nym. (author)

  9. Tritium in underground-water studies; Emploi du tritium dans les etudes sur les eaux souterraines; Tritij v isledovaniyakh podzemnykh vod; Empleo del tritio en el estudio de las aguas subterraneas

    Energy Technology Data Exchange (ETDEWEB)

    Alekseev, F A; Gol' bek, G R; Sojfer, V N; Vasil' eva, N A; Majdebor, V N; Sokolovskij, Eh V; Shan' gin, N N

    1962-01-15

    : infiltracion del agua a traves de los sectores mas permeables del estrato, a velocidades comprendidas entre 10 y 30 m por dia, y avance del contorno basico de agua bombeada en una parte relativamente homogenea del estrato, a una velocidad de 2 m por dia. Este ultimo desplazamiento corresponde a las velocidades (1,9 a 2,2 m por dia) calculadas teoricamente para un estrato homogeneo. Es posible evaluar cuantitativamente el flujo en los desplazamientos de ambos tipos. Se ha ideado un metodo que emplea tritio para observar la comunicacion entre las aguas presentes en los distintos sectores intercalados en el estrato productivo de una vena petrolifera. Los autores proponen un metodo nuevo para controlar la explotacion de yacimientos petroliferos gracias al tritio natural contenido en las aguas superficiales inyectadas en el estrato, tanto en el interior como en el exterior del contorno. El lento desplazamiento del contorno de yacimientos petroliferos grandes, en los que se hayan realizado pocas perforaciones, puede ser estudiado durante periodos largos (unos 10 anos). De la cantidad de tritio desintegrado que contenga el agua subyacente a 1a. capa petrolifera de un pozo en explotacion pueden deducirse los tiempos y velocidades de desplazamiento del agua de contorno con una exactitud de {+-} 1 ano. Basta un numero reducido de analisis (no mas de 300 a 500 analisis por ano en un gran yacimiento) para seguir el desplazamiento del contorno. Se ha ideado un aparato sumamente sensible para medir el tritio en las aguas superficiales con contadores contrastados llenos de liquido. La mayor parte de las organizaciones industriales puede disponer de aparatos de este tipo. (author) [Russian] Izlagaetsya razvitie metoda vodnogo indikatora s ispol'zovaniem iskusstvennogo i prirodnogo tritiya pri izuchenii dvizheniya podzemnykh vod. Ustanovleno dva vozmozhnykh tipa dvizheniya zhidkosti po plastu, protiv vody po naibolee pronitsaemym uchastkam plasta so skorostyami 10/30 m/sutki i prodvizhenie

  10. Design Experience on a Multi-Mecacurie Radiation Facility; Etudes et experiences concernant un emetteur de rayonnements de plusieurs megacuries; Opytnoe proektirovani e ustanovki, obladayushchej sverkhmoshchnym izlucheniem; Estudios sobre el proyecto de un dispositivo de irradiacion de varios megacuries

    Energy Technology Data Exchange (ETDEWEB)

    Brunton, D C; Donovan, J; Voyvodic, L [Curtiss-Wright Corporation, Princeton, NJ (United States); Armour Research Foundation, 10 W. 35th Street, Chicago 10, IL (United States)

    1960-07-15

    tipo placa. Los autores examinan los requisitos tecnicos en lo referente a los dispositivos de transporte de las sustancias en relacion con la estructura de la fuente y con sus efectos sobre el rendimiento. De igual modo estudian los metodos de manipulacion de la fuente, las sistemas de seguridad y los dispositivos de regulacion. Por ultimo, describen la preparacion de la sustancia radiactiva propiamente dicha, comprendida su medicion, introduccion en la capsula y prueba de estanqueidad. (author) [Russian] V dannom dokumente opisyvaetsya rabota po issledovaniyu i razrabotke proekta i stroitel'stva izluchatelya, kotoraya provodilas' v svyazi s proektom ''Vysokointensivnyj izluchatel' dlya pishchevykh produktov''. Obsuzhdaemye problemy yavlyayutsya obshchimi dlya vsekh bol'shikh i malogabaritnykh izluchatelej. Pervaya stadiya raboty po issledovaniyu i razrabotke proekta kasalas' uyasneniya roli diskovogo tipa izluchatelej, a takzhe vliyaniya izmenenij v parametrakh pri sooruzhenii takoj ustanovki. Vnachale sooruzhenie odnogo diskovogo izluchatelya bylo izucheno putem provedeniya teoreticheskogo ehksperimental'nogo i raschetnogo analizov. Izuchennye parametry kasalis' kolichestva iskhodnykh materialov, konkretnoj aktivnosti, tolshchiny istochnika i ego pokrytiya, plotnosti misheni i geometricheskikh faktorov, vklyuchaya vysotu, dlinu i shirinu istochnika, a takzhe razmer vozdushnogo promezhutka mezhdu istochnikom i mishen'yu. Bylo provedeno izuchenie voprosov stroitel'stva , kotorye kasalis' moshchnosti, vremeni prebyvaniya produktov v ustanovke, edinoobraziya dozy, ehffektivnosti i obshchej stoimosti. Byli razrabotany i provereny na opyte uproshchennye sposoby sooruzheniya izluchatelya. Byl razrabotan trekhrazmernyj printsip dlya primeneniya k stroitel'stvu izluchatelya tipa Monte Karlo. EHtot printsip primenyalsya v dannoj probleme s provedeniem sootvetstvuyushchikh ehksperimental'nykh izmerenij. Programma proektirovaniya izluchatelya byla rasshirena dlya vklyucheniya

  11. Case Study in Internal Audit of Nuclear Material; Etude d'un Systeme de Verification Comptable Interne des Matieres Nucleaires; Izuchenie primera organizatsii vnutrennego ucheta yadernykh materialov na predpriyatii; Estudio de la Fiscalizacion Interna de los Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kops, S. [United States Atomic Energy Commission, Argonne, IL (United States)

    1966-02-15

    diversos grupos dentro de la organizacion; se discute, ademas, la cuestion de la distribucion de las informaciones. (author) [Russian] Kratko obsuzhdajutsja obshhaja potrebnost' v organizacii vnutrennej proverki nalichija jadernyh materialov na predprijatii i osnovnye principy administrativno- hozjajst vennogou ch eta. Pri opredelenii potrebnosti v organizacii obychnogo vnutrennego ucheta glavnymi faktorami javljajutsja: razmer predprijatija, ego slozhnost' i stepen' centrali- zacii ili decentralizacii. Obsuzhdajutsja i protivopostavljajutsja vnutrennemu uchetu obych- nogo tipa bolee special'nye trebovanija i osobennosti vnutrennego ucheta, prisushhie predpri- jatiju, raspolagajushhemu radioaktivnymi istochnikami ili special'nymi rasshhepljajushhimisja materialami (jadernymi materialami). Vvidu vysokoj denezhnoj stoimosti i strategicheskoj vazhnosti materialov dokazyvaetsja neobhodimost' organizacii osoboj vnutrennej proverki. Podrobno obsuzhdaetsja planirovanie organizacii vnutrennej proverki na proizvodst- vennom predprijatii. Pomimo vedenija uchetnyh dokumentov i fakticheskoj proverki nalichija materialov, podlezhashhih proverke i vyjavleniju, ob{sup j}asnjajutsja soobrazhenija, lezhashhie v osno- ve ustanovlenija srokov obsledovanij. Obsuzhdajutsja takzhe kvalifikacii i kategorii specia- listov, kotorye dolzhny byt' privlecheny k vypolneniju funkcij vnutrennej proverki. Obsuzhdaetsja konkretnyj statisticheskij plan vybora ob{sup e}ktov dlja ispytanij i prob. Podrobno opisyvaetsja primenenie takih planov k fakticheskomu provedeniju vnutrennej proverki. Obsuzhdajutsja vozmozhnye othody ot obshheprinjatyh norm i vozmozhnye podhody k resheniju problemy. Hotja na mnogih promyshlennyh predprijatijah obychnogo tipa i sushhest- vujut razlichnye metody proverki nalichija materialov bezfizicheskogo ih obsledovanija, dokazyvaetsja neobhodimost' fizicheskogo obsledovanija nalichija jadernyh materialov. Opisyvajutsja razlichnye sposoby predstavlenija otchetovorezul'tatah vnutrennej

  12. Review of Development Status of Nuclear Superheat; Expose sur l'etat actuel des travaux concernant la surchauffe nucleaire; Obzor razrabotki voprosa o yadernykh peregrevatelyakh; Estudio de los progresos realizados en niateria de sobrecalentamiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Imhoff, D. H.; Pennington, R. T. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    1959 goda i iyunem 1962 goda, i itogi obsuzhdeniya znachitel'nykh ehksperimental'nykh rezul'tatov. b). Daetsya kratkoe opisanie rasshirennogo usovershenstovannogo demonstratsionnogo ehksperimenta s peregrevom (E-SADE) pri rabote Vallesitosskogo reaktora s kipyashchej vodoj, privodyatsya tablitsy ehkspluatatsionnykh uslovij, dannye o toplivnykh ehlementakh, obluchennykh na ustanovke E-SADE, i itogi obsuzhdeniya znachitel'nykh rezul'tatov prodelannoj raboty. c) Daetsya kratkoe opisanie reaktora Ehmpajr Stejts Atomik Development Assoshiejts-Vallesitos- skogo ehksperimental'nogo reaktora s peregrevom (ESAD-VESR), privoditsya spisok ozhidaemykh rabochikh uslovij, vklyuchaya konstruktsionnye usloviya pervonachal'noj zagruzki aktivnoj zony s peregrevom, i otchet o tekushchem sostoyanii stroitel'nykh rabot.

  13. Measurements of Void Effects in the Zero-Power Critical Facility NORA; Mesures de l'Effet Cavitaire dans l'Ensemble Critique NORA de Puissance Zero; Izmerenie vliyaniya pustot v kriticheskoj ustanovke nulevoj moshchnosti NORA; DeterminaciOn de los Efectos de CavitaciOn en el Conjunto Critico NORA de Potencia Nula

    Energy Technology Data Exchange (ETDEWEB)

    Bryhn-Ingebrigtsen, K.; Eriksen, V. O.; Schatvet, J.; Ukkestad, A.; Wood, J. I.; Ofjord, K. [Kjeller Research Establishment (Norway)

    1964-02-15

    influencia de los vacios sobre la reactividad asume particular importancia en los reactores de agua hirviente. La distribucion no uniforme de los vacios aconseja investigar y comprender la ley de variacion espacial del efecto cavitario sobre la reactividad. En la instalacion NORA se ha llevado a cabo un estudio experimental del efecto cavitario en condiciones fisicamente 'limpias'. En las zonas tubulares comprendidas entre las barras de combustible y sus envolturas se crean cavidades por inyeccion de aire comprimido. En los experimentos de barra unica, los efectos de reactividad son tan pequeflos que es preferible producir periodicamente impulsos oscilantes en el volumen cavitario y analizar la modulacion de potencia correspondiente para obtener los coeficientes de reactividad equivalentes. En el caso de las barras multiples, los experimentos se efectuan por procedimientos estaticos. Los autores describen la tecnica experimental y dan ejemplos de su aplicacion en la determinacion de los efectos cavitarios para una sola barra, las interacciones en el caso de las barras alrededor de las cuales se han formado cavidades y los efectos de las cavidades creadas en toda la extension del cuerpo. (author) [Russian] Vliyanie pustot na velichinu reaktivnosti v aktivnoj zone reaktora igraet ochen' vazhnuyu rol' v kipyashchikh reaktorakh. Neravnomernoe raspredelenie pustot delaet ne- obkhodimym izuchenie i uyasnenie prostranstvennoj zavisimosti vliyaniya pustot na velichinu reaktivnosti. Izuchalos' vliyanie pustot pri chistykh v fizicheskom otnoshenii usloviyakh v ustanovke NORA. EHkrany, okruzhayushchie kazhdyj otdel'nyj toplivnyj stringer, opredelyayut kol'tsevye Oblasti, v kotorykh sozdayutsya pustoty putem vvedeniya vozdukha pod davleniem. V opytakh s otdel'nym sterzhnem ehffekty reaktivnosti nastol'ko maly, chto predpoch- titel'no periodicheski izmenyat' ob{sup e}m pustoty i analizirovat' sootvetstvuyushchuyu modulyatsiyu ehnergii s tsel'yu poluchit' ehkvivalent reaktivnosti. Opyty s

  14. Properties of Waste from Coal Gasification in Entrained Flow Reactors in the Aspect of Their Use in Mining Technology / Właściwości odpadów ze zgazowania węgla w reaktorach dyspersyjnych w aspekcie ich wykorzystania w technologiach górniczych

    Science.gov (United States)

    Pomykała, Radosław

    2013-06-01

    Most of the coal gasification plants based of one of the three main types of reactors: fixed bed, fluidized bed or entrained flow. In recent years, the last ones, which works as "slagging" reactors (due to the form of generated waste), are very popular among commercial installations. The article discusses the characteristics of the waste from coal gasification in entrained flow reactors, obtained from three foreign installations. The studies was conducted in terms of the possibilities of use these wastes in mining technologies, characteristic for Polish underground coal mines. The results were compared with the requirements of Polish Standards for the materials used in hydraulic backfill as well as suspension technology: solidification backfill and mixtures for gob caulking. Większość przemysłowych instalacji zgazowania węgla pracuje w oparciu o jeden z trzech głównych typów reaktorów: ze złożem stałym, dyspersyjny lub fluidalny. W zależności od rodzaju reaktora oraz szczegółowych rozwiązań instalacji, powstające uboczne produkty zgazowania mogą mieć różną postać. Zależy ona w dużej mierze od stosunku temperatury pracy reaktora do temperatury topnienia części mineralnych zawartych w paliwie, czyli do temperatury mięknienia i topnienia popiołu. W ostatnich latach bardzo dużą popularność wśród instalacji komercyjnych zdobywają reaktory dyspersyjne "żużlujące". W takich instalacjach żużel jest wychwytywany i studzony po wypłynięciu z reaktora. W niektórych przypadkach oprócz żużla powstaje jeszcze popiół lotny, wychwytywany w systemach odprowadzania spalin. Może być on pozyskiwany oddzielnie lub też zawracany do komory reaktora, gdzie ulega stopieniu. Wszystkie z analizowanych odpadów - trzy żużle oraz popiół pochodzą właśnie z tego typu instalacji. Tylko z jednej z nich pozyskano zarówno żużel jak i popiół, z pozostałych dwóch jedynie żużel. Odpady te powstały, jako uboczny produkt zgazowania w

  15. The Determination of Uranium in Urine by Delayed Neutron Counting; Dosage de l'Uranium dans l'Urine par Comptage des Neutrons Differes; Opredelenie soderzhaniya urana v moche putem scheta zapazdyvayushchikh nejtronov; Determinacion del Uranio Contenido en la Orina por Recuento de Neutrones Retardados

    Energy Technology Data Exchange (ETDEWEB)

    Brookes, I. R. [Atomic Weapons Research Establishment, Aldermaston, Berks. (United Kingdom)

    1965-10-15

    recipiente adecuado y se introduce por un sistema de tubos neumaticos en el nucleo del reactor HERALD, donde es irradiado en un flujo termico de 3,94 * 10{sup 12}n/cm{sup 2} s, aproximadamente. Al cabo de 1 min de irradiacion la muestra vuelve automaticamente al laboratorio, donde el frasco que la.contiene se coloca en el contador neutronico que se conecta a los 25 s de haber salido la muestra del reactor. La muestra se recuenta durante 1 min. Las muestras testigo consisten en orina de personas no expuestas profesionalmente al uranio, y el patron de calibracion, en una cantidad conocida de {sup 235}U (en forma de uranio natural). El limite de deteccion es de 0,020 pCi de uranio enriquecido al 93% (0,007 de la carga corporal maxima admisible) y 0,036 {mu}g de uranio natural por 100 mi de orina. El limite de deteccion depende de la' actividad de la muestra testigo determinada por recuento. La actividad principal de la muestra testigo se debe a los emisores gamma formados por irradiacion de la orina. El ciclo de irradiacion y recuento dura unos 3,5 min y en una jornada de trabajo se pueden evaporar y envasar 50 muestras. A los efectos del analisis de orina, es despreciable la interferencia del {sup 239}Pu. (author) [Russian] Pri jetom metode soderzhanie urana-235 opredeljaetsja putem scheta zapazdyvajushhih nejtronov, ispuskaemyh posle delenija urana-235 v obrazce teplovymi nejtronami. Tri gruppy nejtronov, predstavljajushhie interes, imejut periody poluraspada 55,72, 22,72 i 6,22 sek. 100 ml mochi isparjajut do suhogo ostatka v vodjanoj vanne. Ostatok pomeshhajut v. polijetilenovuju butylku vesom v odnu unciju vmeste primerno s 4 - 5 ml, a zatem butylku zapaivajut v gorjachem sostojanii. Butylku s obrazcom pomeshhajut v kontejner i napravljajut cherez sistemu pnevmaticheskih trub v aktivnuju zonu reaktora HERALD,gde ona obluchaetsja v potoke teplovyh nejtronov, sostavljajushhem priblizitel'no 3,94 * 10{sup 12} n/sm{sup 2} sek. Posle obluchenija v techenie odnoj minuty obrazec

  16. Assessment of End-Plug Welding of Fuel Elements; Evaluation des Soudures Terminales des Elements Combustibles; Otsenka kachestva privarki kontsevoj probki toplivnykh ehlementov; Inspeccion de la Soldadura del Tapon Terminal de los Elementos Combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Y.; Aoki, T. [Tokai Refinery, Atomic Fuel Corporation (Japan)

    1965-10-15

    investigacion Numero-Sign 3 (JRR-3). Ese reactor de 10 MW es moderado y refrigerado por agua pesada, y tiene elementos combustibles de uranio metalico revestidos de aluminio. Como entre el revestimiento y el alma hay solamente una union mecanica, puede producirse una tension en el tapon terminal como resultado del crecimiento del alma de uranio debido a la irradiacion. El ciclo termico produce tensiones analogas en las soldaduras. Como resultado de la diferencia de microestructura, las proximidades de estas que dan especialmente expuestas a la corrosion producida por el agua caliente. Mientras el reactor esta en servicio, es imprescindible asegurar su estanqueidad. Se han utilizado probetas especiales para estudiar la resistencia a la traccion, la fluencia a alta temperatura, los efectos del ciclo termico y la corrosion. Antes de hacer esos ensayos, y periodicamente durante su realizacion, se sometieron a examen no destructivo muchas clases de soldaduras y se verifico si habia escapes. La evaluacion de los resultados obtenidos puede servir para establecer normas de inspeccion, por ejemplo, mediante radiografia y examen visual de la soldadura del tapon. En la memoria se describen algunos otros resultados de ensayos efectuados con elementos combustibles revestidos de Magnox y Zircaloy. (author) [Russian] Ochen' vazhno ustanovit' sootnoshenie mezhdu rezul'tatami ispytanij i ispol'zovaniem ih v reaktore, a takzhe razrabotat' sami metody ispytanija bez razrushenija ispytyvaemogo ob{sup e}kta. Odnako sdelat' jeto dovol'no trudno, tak kak jeto svjazano s bol'shimi rashodami i bol'shoj radioaktivnost'ju. Bylo proizvedeno neskol'ko vidov ocenok vo vnereaktornom sostojanii s imitaciej vnutrireaktornyh uslovij. Opisyvajutsja nekotorye detali jetih ocenok v otnoshenii toplivnyh jelementov issledo- vatel'skogo reaktora JKK-3. V je t om reaktore ustanovlennoj moshhnost'ju 10 mgvt s tjazhe- loj vodoj v kachestve zamedlitelja i teplonositelja ispol'zujutsja toplivnye jelementy iz

  17. A Method of Identification and Inspection for Inventory Control of Irradiated Fuel Elements; Methode d'Identification et d'Inspection Permettant de Proceder a l'Inventaire des Elements Combustibles Irradies; Metod identifikatsii i proverki pri inventarnom kontrole obluchennykh toplivnykh ehlementov; Metodos de Identificacion e Inspeccion para el Control de las Existencias de Elementos Combustibles Irradiados

    Energy Technology Data Exchange (ETDEWEB)

    Kinderman, E. M.; Mills, J. S. [Stanford Research Institute, Menlo Park, CA (United States)

    1966-02-15

    punto de descarga del reactor y el de almacenamiento del combustible. Pero esos dos lugares presentan dificultades materiales de caracter peculiar para los inspectores o los encargados de controlar el inventario. La distancia entre el objeto y el observador, la escasa iluminacion y l a distorsion optica debida a los medios de blindaje (agua, cristal) son factores que contribuyen a dificultar las operaciones inherentes al inventario de materiales. Para resolver estas dificultades y poder identificar positivamente el combustible descargado de un reactor, los autores han ideado un dispositivo de inspeccion optica compuesto de una estacion fija, un periscopio, un telescopio y una camara fotografica. Con este dispositivo se han hecho pruebas en una pileta de irradiacion por cobalto en las que se han examinado varias muestras marcadas diversamente y tratadas en un circuito de agua caliente. Para estas pruebas se emplearon un periscopio lleno de agua, de 3,35 m de longitud, un telescopio catadioptrico colocado a 4,9 m del periscopio, y una camara de 35 mm para registrar las observaciones. El telescopio, la camara y los soportes son portatiles, pues pesan en total menos de 10 kg y su dimension maxima es de 75 cm. Las observaciones fotograficas de diagramas de resolucion tomadas como pruebas en aire, a 6 m del objetivo del telescopio, pusieron de manifiesto que ese sistema puede resolver senales de comprobacion de 22 {mu}m de ancho, lo que corresponde a una resolucion de 0,8 segundos de arco. Ensayos llevados a cabo con el dispositivo sumergido en agua mostraron que en este caso el poder de resolucion es superior a 50 {mu}m a 6 m, lo que corresponde a una resolucion de 1 segundo de arco, Es evidente que el poder de resolucion nunca puede ser superior al del sistema en aire. El sistema descrito empleado en un inventario real de combustible, reproducira adecuadamente cualquier senal de comprobacion. (author) [Russian] Mesta razgruzki reaktora i hranenija obluchennogo topliva

  18. Svojstva i struktura wolframkarbid-kobalt prevlake deponovane plazma-sprej postupkom

    Directory of Open Access Journals (Sweden)

    Mihailo Rade Mrdak

    2013-10-01

    rezultati su bili  usrednjeni. Testovi zatezne čvrstoće rađeni su na sobnoj temperaturi na hidrauličnoj opremi sa brzinom od 10 mm/min. Korišćena su dva uzoraka u paru, od kojih je prevlaka deponovana samo na jednom od njih. Za svaku grupu WC17Co prevlaka ispitano je po pet uzoraka, a dobijeni rezultati su usrednjeni. Metalografska procena udela pora (image analiza u slojevima WC17Co prevlaka urađena je tehnikom svetlosne mikroskopije u skladu sa standardom Pratt & Whitney (Turbojet Engine – Standard Practices Manual (PN 582005, 2002, Pratt & Whitney, East Hartford, USA. Morfologija čestica praha urađena je na SEM-u (skening elektronskom mikroskopu. Depozicija praha Proces deponovanja slojeva na metalne osnove urađen je plazma-sprej postupkom na atmosferskom pritisku (APS firme Plasmadyne. Depozicija praha urađena je plazma pištoljem SG-100 koji se sastojao od katode tipa K 1083A -129 , anode tipa A 2083-175 i gas-injektora tipa  GI 1083-113. Kao gas korišćen je argon u kombinaciji sa helijumom i snaga napajanja od 40 KW. Protok plazma gasa helijuma bio je osnovni parameter za deponovanje praha. U eksperimentu su korišćena tri različita protoka helijuma od 12 l/min, 22 l/min i 32 l/min. Slojevi su deponovani na supstratima ukupne debljine od 0,020 do 0,025 mm sa plazma pištoljem brzine 500 mm/s. Rezultati i diskusija Vrednosti mikrotvrdoće i čvrstoće spoja deponovanih slojeva su u direktnoj vezi sa protocima helijuma kao plazma gasa. Svi deponovani slojevi imaju vrednosti mikrotvrdoće u propisanim granicama od 850 do 1300 HV0.3 (Material Product Data Sheet, 2011, (Turbojet engine-standard practices manuel TURBOMECA.  Najravnomerniju raspodelu mikrotvrdoće imali su slojevi deponovani sa protokom plazma gasa od 22 l/min.He. Ti slojevi su imali najmanju razliku  mikrotvrdoće između maksimalnih i minimalnih vrednosti (289 HV0.3. Najveću raspodelu mikrotvrdoće pokazali su slojevi  deponovani sa najvećim protokom plazma gasa od 32 l/min He. Ti

  19. Maestro di Pico i iluminacije u inkunabuli De Civitate Dei (Nicolas Jenson, Venecija, 1475. u samostanu Sv. Duje u Kraju na Pašmanu

    Directory of Open Access Journals (Sweden)

    Bojan Goja

    2014-12-01

    Full Text Available U franjevačkom samostanu Sv. Duje u Kraju na otoku Pašmanu čuva se inkunabula „O državi Božjoj“ (De Civitate Dei Sv. Aurelija Augustina koju je 1475. godine u Veneciji tiskao Nicolas Jenson. Inkunabula je na f. 17 (kako je naknadno označena paginacija grafitnom olovkom, tj. stranici incipita – liber primus kao i na više drugih stranica ukrašena lijepim višebojnim iluminacijama renesansnih stilskih karakteristika izrađenih temperom, zlatnim listićima, zlatnim prahom, sepijom, tintom i akvarelom. Iluminacije f. 17 sastoje se od dva fitomorfna inicijala, dekorativnog okvira i slobodnih figurativnih prizora tj. minijatura, dok su pojedine druge stranice ukrašene fitomorfnim i brojnim inicijala tipa littera notabilior visine dva retka izrađenima u crvenoj ili plavoj boji. Dekorativni ornamentirani okvir zaključen trolistima ispunjava gornju i lijevu marginu početne stranice. Osnovu dekoracije čini traka sastavljena od pet tankih linija koja se spiralno povija i tvori kružnice koje su ispunjene cvjetovima, listovima i bobicama u plavoj i zelenoj boji i boji ciklame te stiliziranim zlatnim cvjetovima čička (lat. Arctium lappa; pojedini autori nazivaju ove ukrasne motive bottoni dorati ili gold dots. U gornjem lijevom uglu okvira naslikan je češljugar. Na mjestu gdje započinje tekst lijevog stupca naslikan je unutar pravokutnog polja na zlatnoj pozadini inicijal „I“ sastavljen od fitomorfnih motiva plave, zelene i boje ciklame s osjenčanjima u različitim nijansama. Unutar dekorativnog okvira, na sredini visine inicijala, nalazi se medaljon unutar kojeg je naslikano poprsje Sv. Aurelija Augustina. Dekorativni ornamentirani okvir koji ispunjava gornju marginu ukrašen je na isti način kao i onaj uz desnu ali skromnije. Ime tiskara dodatno je naznačeno tako da je sa gornje i donje strane okvira ukrašeno sa po jednim stiliziranim zlatnim cvijetom čička sa gornje i češljugovine (lat. Dipsacus fullonum sa donje strane

  20. Injection of Plasma Blobs into A Mirror Trap With Adiabatic Plasma Compression: ''ASPA'' Device; Injection d'Amas de Plasma dans un Piege a Miroirs avec Compression Adiaba Tique - Machine 'ASPA'; Inzhektsiya plazmennykh sgustkov v probochnuyu lovushku s adiabaticheskim szhatiem plazmy. Ustanovka ''ASPA''; Inyeccion de Plasmoides en una Trampa de Espejos con Compresion Adiabatica. La Instalacion 'ASPA'

    Energy Technology Data Exchange (ETDEWEB)

    Babichev, A. P.; Burjak, E. M.; Gorbunova, E. F.; Karchevskij, A. I.; Muromkin, Ju. A. [Institut Atomnoj Ehnergii, Im. I.V. Kurchatova, Moskva, SSSR (Russian Federation)

    1966-04-15

    kotorymi 20 sm (probochnoe otnoshenie 1:2). Maksimal'naja naprjazhennost' impul'snogo magnitnogo polja v probkah sostavljaet 40 kje, vremja narastanija magnitnogo polja Tilde-Operator 40 mksek, a vremja spada polja 350 mksek. Provodilis' mass-spektrometricheskie issledovanija sostava i jenergeticheskih raspredelenij ionnoj komponenty plazmy v titanovom i koaksial'nom inzhektorah. S pomoshh'ju mikrovolnovogo interferometra izmerjalas' plotnost' plazmennogo sgustka pri ego dvizhenii ot inzhektora k rabochej oblasti szhatija. Issledovalos', takzhe, prohozhdenie plazmennogo sgustka cherez magnitnuju probku s naprjazhennost'ju polja do 20 kje. V odnih opytah pole probki bylo parallel'no vedushhemu magnitnomu polju, a v drugih - antiparallel'no, t.e. sozdavalos'' pole divertornogo tipa s dvumja oblastjami nulevoj naprjazhennosti polja. Pokazano, chto inzhektiruemyj plazmennyj sgustok (kak dlja titanovogo, tak i dlja koaksial'nogo inzhektorov) otnositel'no svobodno pronikaet cherez magnitnuju probku, kogda pole probki sovpadaet po napravleniju s vedushhim magnitnym polem; i prakticheski ne prohodit v sluchae polja divertornogo tipa. Na osnovanii jetih opytov pokazana vozmozhnost' otsechki tjazhelyh primesej inzhektiruemoj plazmy s pomoshh'ju impul'snogo magnitnogo zatvora, sozdajushhego oblasti s nulevoj naprjazhennost'ju magnitnogo polja i vyhodom magnitnyh silovyh linij na stenki kamery. V predvaritel'nyh jeksperimentah po adiabaticheskomu szhatiju plazmy v lovushke probochnoj konfiguracii zaregistrirovano zhestkoe rentgenovskoe izluchenie (jenergija 30 kjev) i issledovano vlijanie nachal'nogo magnitnogo polja i parametrov plazmennogo sgustka na intensivnost' i zhestkost' jetogo izluchenija. (author)

  1. Application of radioisotopes to the investigation of the kinetics and mechanism of reactions of some inorganic complex compounds; Application des radioisotopes a l'etude de la cinetique et du mecanisme des reactions de certains complexes inorganiques; Primenenie radioizotopov k issledovaniyam kinetiki i mekhanizma reaktsij nekotorykh neorganicheskikh slozhnykh soedinenij; Aplicacion de los radioisotopos al estudio de la cinetica y del mecanismo de las reacciones de algunos complejos inorganicos

    Energy Technology Data Exchange (ETDEWEB)

    Harris, Gordon M [Department of Chemistry, University of Buffalo, Buffalo 14, NY (United States)

    1962-03-15

    estado de equilibrio, efectuada en la reaccion de intercambio de carbonatos. De la misma manera, los datos relativos al efecto cinetico de los isotopos en la hidratacion del ion Co(NH{sub 3}){sub 4}CO{sub 3}{sup +} catalizada por acidos han corroborado las teorias sobre el caracter de la fase de ruptura de enlaces, que determina la velocidad de estas reacciones. Por ultimo, los experimentos con trazadores radiactivos facilitan frecuentemente el estudio de las posiciones sucesivas de ciertos atomos o radicales en las reacciones inorganicas para las que existen diversas explicaciones teoricamente posibles. Como ejemplo puede citarse la demostracion de que en la oxidacion del ion tiocianato por peroxido de hidrogeno, el cianuro no es un producto intermedio que sufre un intercambio rapido a pesar de que constituye uno de los principales productos finales. (author) [Russian] Ispol'zovanie radioizotopov okazyvaet neotsenimye uslugi pri issledovanii khimicheskikh neorganicheskikh reaktsij samykh raznoobraznykh vidov i, v chastnosti, reaktsij so slozhnymi ionizirovannymi veshchestvami v vodnykh rastvorakh. Odnim iz vazhnykh metodov sluzhit izuchenie skorosti i mekhanizma protsessov izotopnogo obmena. Tak, naprimer, byl proveden ryad issledovanij obmen a mezhdu t.n. ''svobodnym'' karbonatom, mechennym uglerodom-14, i svyazyvayushchim karbonatom oktaehdral'nykh slozhnykh ionov tipa CoA{sub 2}CO{sub 3}{sup +}, gde A = 2 NH{sub 3}, ehtilendiamin (en), propilendiamin (pn) ili trimetilendiamin (tn). EHti issledovaniya priveli k dovol'no tochnomu ponimaniyu kharaktera reaktsij ehtogo roda po zamene svyazi, a takzhe roli v ehtoj reaktsii neuchastvuyushchikh v obmene svyazyvayushchikh aminovykh zven'ev. Analogichnye issledovaniya obmena oksalatov, provedennye so slozhnymi trioaksalatami tipa M (C{sub 2}O{sub 4}){sub 3}{sup -3}, gde M=Co (III), Cr (III) ili Br (III), dali stol' zhe plodotvornye rezul'taty. Drugim metodom, primenimym tol'ko v sluchae ispol'zovaniya radioizotopov s malym

  2. Comparison Of The Worth Of Critical And Exponential Measurements For Heavy-Water-Moderated Reactors; Valeur Relative des Mesures Critiques et Exponentielles pour l'Etude des Reacteurs Ralentis a l'Eau Lourde; Sravnenie tsennosti kriticheskikh i ehksponentsial'nykh izmerenij dlya reaktorov s tyazhelovodnym zamedlitelem; Valor Relativo de las Mediciones Criticas y Exponenciales para los Reactores Moderados por Agua Pesada

    Energy Technology Data Exchange (ETDEWEB)

    Graves, W. E.; Hennelly, E. J. [Savannah River Laboratory, E.I. Du Pont De Nemours and Co., Aiken, SC (United States)

    1964-02-15

    izmerenijah tipa PCTR. V jeksponencial'nyh izmerenijah trudnosti, po-vidimomu, zakljuchajutsja edinstvenno v opredelenii radial'nogo laplasiana. Pri udachnom vypolnenii jeksponencial'nye izmerenija mogut uspeshno konkurirovat' s kriticheskimi. Naibol'shee kolichestvo materiala trebuetsja dlja odnozonnyh kriticheskih izmerenij, primerno odinakovoe kolichestvo-dlja podstanovochnokriticheskih i jeksponencial'nyh izmerenij i menee vsego-dlja izmerenij tipa PCTR. 2) Anizotropnyj i pustotnyj jeffekty Sravnenija jeksperimentov laboratorii s kriticheskimi i kriticheski-jeksponencial'nymi privodjatsja v dannoj rabote, a bolee podrobno oni izlagajutsja v rabote, kotoraja soprovozhdaet dannuju. 3) Ocenka sistem upravlenija Okazalos, chto horosho proanalizirovannye jeksponencial'nye jeksperimenty dajut horoshie rezul'taty dlja izmerenij obshhej znachimosti. Odnako dlja nadlezhashhego izuchenija formirovan- nija obshhego potoka, uglov naklona potoka i t.d. neobhodima polnomasshtabnaja kriticheskaja ustanovka napodobie PDP. 4) Temperaturnye kojefficienty Jeksponencial'nye jeksperimenty javljajutsja prevoshodnym metodom opredelenija temperaturnogo kojefficienta laplasiana dlja nagrevanija odnorodnoj reshetki. Imejushhajasja v laboratorii special'naja ustanovka PSE pozvoljaet proizvodit' takie izmerenija vplot' do temperatury 215 Degree-Sign S. Dlja nagrevanija neodnorodnyh reshetok predpovtenie, kak pravilo, otdavalos' kriticheskim jeksperimentam. 5) Smeshannye reshetki Dlja nastojashhih reaktorov redko primenjajutsja prostye odnorodnye reshetki, dlja kotoryh ispol'zujutsja v osnovnom jeksponencial'nye izmerenija. Kriticheskie jeksperimenty so smeshannymi zagruzkami ispol'zujutsja kak dlja izmerenija prjamyh jeffektov v maketah, tak i dlja ispytanija raschetov geterogennoj i dvuhrazmernoj diffuzii. 6) Issledovanija kritichnosti topliva, ispol'zuemogo v tjazhelovodnyh reshetkah, v obychnoj vode vode Jeksponencial'nye izmerenija okazalis' osobenno cennymi dlja issledovanija kritichnosti s cel

  3. Recent Developments in the Chemical Thermodynamics of the Uranium Chalcogenides; Progres Accomplis Recemment dans la Thermodynamique Chimique des Chalcogenures d'Uranium; Poslednie dostizheniya v khimicheskoj termodinamike khal'kogenidov Urana; Recientes Progresos en la Termodinamica Quimica de los Calcogenidos de Uranio

    Energy Technology Data Exchange (ETDEWEB)

    Westrum, Jr., E. F. [University of Michigan, Ann Arbor, MI (United States)

    1966-02-15

    estado ferromagnetico y contrastan con la anomalia antiferro- magnetica hallada en el mononitruro isoestructural a 52 Degree-Sign K. Los nuevos datos termodinamicos concuerdan satisfactoriamente con los obtenidos mediante el procedimiento de evaluacion de entropia de Gronvold y Westrum. (author) [Russian] Rasprostranenie kriotermicheskih dannyh no U{sub 4}O{sub 9} na bolee vysokie temperatury pokazalo termofizicheskie aspekty (predpolagaemogo) postepennogo strukturnogo prevrashhenija tipa-A. pri temperature 348 Degree-Sign K s sootvetstvujushhim prirashheniem jentropii v razmere 1,84 kalorij/gramm-mol' OK, svjazannogo so smeshheniem vnedrennyh atomov kisloroda. Izmerenija kak teploemkosti, tak i magnitnoj vospriimchivosti na spechennoj dvuokisi urana Mol- linkrodta podtverdili, chto antiferromagnitnyj-paramagnitnyj perehod proishodit pri 30,4 Degree-Sign K so skachkom teploemkosti v 400 kalorij/gramm-mol' Degree-Sign K, a ne pri 28,7 Degree-Sign K s povysheniem teploemkosti na devjat' kalorij/gramm-mol' Degree-Sign K, kak soobshhalos' v literature. Jeto pozvoljaet teper' ob{sup j}asnit' termicheskuju anomaliju, obnaruzhennuju v {beta} -U{sub 3}O{sub 7}. Kriogennye teploemkosti, poluchennye na harakternyh obrazcah {alpha}-, {beta}-, i {gamma} utriokisi urana, podgotovlennyh doktorom E.G.P.Kordfunke iz Niderlandskogo reaktornogo centra, kombinirujutsja s teploemkostjami pri bolee vysokoj temperature, jental'pijami obrazovanija i drugimi termodinamicheskimi dannymi dlja poluchenija dannyh ob otnositel'noj stabil'nosti jetih vazhnyh jadernyh materialov. Obnaruzheno, chto kak monoselenid urana, tak i diselenid urana imejut anomalii tipa ljambda, svjazannye s magnitnym razuporjadocheniem. V diselenide urana jeto proishodit pri 13,1 Degree-Sign K s prirashheniem jentropii v 0,16 kalorij/gramm-mol' Degree-Sign K. Prirashhenie jentropii v monoselenide pri anomalii pri 160 Degree-Sign K sostavljaet velichinu 1,0 kalorij/gramm- mol' Degree-Sign K, chto mozhno sravnit' s velichinoj

  4. Thermoluminescent Dosimeter as the Gamma Component of a Nuclear Accident Dosimeter; Utilisation du Dosimetre Thermoluminescent Comme Element Detecteur Gamma d'un Dosimetre pour les cas d'Accident Nucleaire; 0422 0415 0420 041c 0414 ; Los Detectores de Termoluminiscencia Como Elemento Gammametrico de un Dosimetro para Casos de Accidente Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Handloser, J. S. [Edgerton, Germeshausen and Grier, Inc., Santa Barbara, CA (United States)

    1965-06-15

    diametro quetiueda hermeticamente cerrado, con el fosforo en su interior. Este dosimetro mide 0,8 mm de diametro y 6 mm de longitud. El autor ha disenado blindajes destinados a corregir la respuesta energetica de estos dos dosimetros. (author) [Russian] Ispol'zovalis' razlichnye tipy gamma-dozimetrov v kachestve komponenta avarijnyh dozimetrov, izmerjajushhih gamma-izluchenie. Oni vkljuchali razlichnye vidy stekljannyh, plenochnyh, himicheskih dozimetrov i dozimetrov polimerizacii. Termo- ljuminiscentnyj dozimetr obladaet znachitel'nymi preimushhestvami po sravneniju s dozimetrami drugih tipov. Shirokij diapazon termoljuminiscentnogo dozimetra daet vozmozhnost' ispol'zovat' ego v kachestve povsednevnogo kontrol'no-izmeritel'nogo pribora i v kachestve avarijnogo dozimetra. Pri jetom otpadaet nadobnost' v special'noj apparature dlja avarijnoj dozimetrii i sozdaetsja vozmozhnost' ispol'zovat' v avarijnoj dozimetricheskoj sisteme horosho kalibrovannye pribory povsednevnogo ispol'zovanija. Obychno diapazon, prisushhij termo- ljuminiscentnomu dozimetru, kolebletsja ot 5 mr do 100 000 r pri vosproizvodimosti {+-}10%. Byl sproektirovan i izgotovlen edinichnyj tip dozimetra s o ftoristym kal'ciem i s neobhodimym prisposobleniem dlja snjatija pokazanij, v diapazone ot 5 mr do 5000 r . Chtenie pokazanij dozimetra proizvoditsja putem nagreva fosfora i izmereniem vyhoda sveta. Imejutsja pribory dlja registracii pokazanij shesti porjadkov, i sproektirovany polnost'ju avtomatizirovannye sistemy. Ni odin iz priborov ne trebuet dlja opredelenija pokazanij bolee 20 sek na dozimetr. Drugoe preimushhestvo termoljuminiscentnogo dozimetra sostoit v maloj chuvstvitel'nosti k nejtronam. Ona kolebletsja v zavisimosti ot tipa kontejnera i tipa fosfora. Odin tip dozimetra s ftoristym kal'ciem obladaet nejtronnoj chuvstvitel'nost'ju, ravnoj 0,27 * 10{sup -9} r ad /n/cm{sup 2}. Rassmatrivajutsja dva termoljuminiscentnyh dozimetra razlichnyh fizicheskih form. Pervyj predstavljaet soboj nagrevaemyj

  5. Use of semiconductors in lieu of emulsions in nuclear spectroscopy; Utilisation de semi-conducteurs a la place d'emulsions en spectroscopie nucleaire; Primenenie poluprovodnikov vmesto ehmul'sij v yadernoj spektroskopii; Sustitucion de las emulsiones por semiconductores en espectroscopia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Bilaniuk, O M; Marsh, B B [University of Rochester, Rochester, NY (United States)

    1962-04-15

    corrientes de salida excitan un convertidor de tiempo en amplitud de impulso 6BN6. El amplificador de parada contiene un retardo fijo de 2,5 {mu}s que garantiza que el impulso de parada siempre llegue al convertidor despues que el impulso de puesta en marcha. La amplitud del impulso que sale del convertidor 6BN6 es proporcional al intervalo de tiempo entre los impulsos de puesta en marcha y de parada, de modo que las senales que se producen en los diversos contadores del mosaico quedan identificadas por la amplitud del impulso que generan. Los grupos de cuentas resultantes se hacen visibles en la pantalla de un analizador de amplitudes de impulso de 400 canales, se imprimen, y se registran graficamente en un sistema de coordenadas ortogonales. Los grupos quedan enteramente resueltos, asi que la identificacion es completa. El circuito de identificacion es capaz de admitir un impulso cada 8 {mu}s, por lo que la limitacion de velocidad de contaje no se debe a el, sino al analizador de 400 canales. Los autores han encontrado que el sistema de identificacion funciona satisfactoriamente en presencia del campo magnetico y estando el ciclotron en plena marcha. Describen todos los circuitos del sistema de identificacion y presentan ejemplos de datos nucleares obtenidos con este dispositivo. (author) [Russian] Dvadtsat' poverkhnostno-bar'ernykh schetchikov, poluchennykh putem pokrytiya germaniya tipa ''n'' tonkim sloem zolota (nakhodyashchegosya v gazoobraznom sostoyanii), ili schetchiki s ploskostnym perekhodom, poluchaemye posredstvom diffuzii fosfora v kremnij tipa ,''p'', pomeshchayutsya v zerkal'nuyu ploskost' magnitnogo spektrometra s vysokoj razreshayushchej sposobnost'yu vmesto yadernoj ehmul'sionnoj plastiny. S tsel'yu izbezhat' primeneniya otdel'nykh usilitelej i registrov dlya kazhdogo kristalla vykhody otdel'nykh schetchikov soedinyayutsya v sosredotochennuyu liniyu zaderzhki, zamenyaya chereduyushchiesya kondensatory linij. Kogda ioniziruyushchaya chastitsa udaryaetsya o

  6. Release of Fission Products from UC-ZrC Fuel Inserts; Degagement des produits de fission liberes dans des noyaux combustibles UC-ZrC; Vydelenie produktov deleniya iz topliv UC - ZrC; Liberacion de productos de fision por pastillas de combustible de UC-ZrC

    Energy Technology Data Exchange (ETDEWEB)

    Barth, F.; Von der Decken, C. B.; Schifferstein, K. [Brown Boveri/Krupp Reaktorbau G.M.B.H., Duesseldorf (Germany); Clauss, A.; Reichel, H.; Rygaert, J.; Ruston, W. R. [Societe d' Etudes de Recherches et d' Applications pour l' Industrie (S.E.R.A.I.), Brussels (Belgium)

    1963-11-15

    hallaron grandes diferencias en las energias de activacion determinadas en distintos tipos de pastillas, aunque algunas veces los valores D/r{sub 0}{sup 2} paragraph diferian en cuatro ordenes de magnitud para una misma temperatura de la muestra. Despues de la irradiacion, se determinaron las actividades de los isotopos {sup 131}I, {sup 85}Sr, {sup 140}Ba y {sup 141}Ce en el grafito de las capsulas. Exceptuando el {sup 131}I, las actividades resultaron superiores a las previstas para un desprendimiento debido solamente a retroceso. Los valores correspondientes al {sup 89}Sr, {sup 140}Ba y {sup 141}Ce son damasiado altos para que puedan atribuirse a una difusion de loe respectivos gases nobles precursores. Se supone que los isotopos medidos, o sus precursores distintos de los gases nobles se desprendieron por difusion. (author) [Russian] Provedeno issledovanie vo vremya oblucheniya v petle vydeleniya produktov deleniya ieh tabletok, imeyushchikh priblizitel'nyj sostav UC + 20 ZrC. Tsel' - proverka vozmozhnosti ispol'zovaniya podobnykh tabletok v kachestve topliva v sfericheskikh teplovydelyayushchikh ehlementakh vysokotemperaturnogo reaktora, postroennogo v Yulikhe ''Obshchestvom stroitel'stva reaktorov Braun Boveri/Krupp''. Ispytaniyu podvergalis' svobodnye tabletki i tabletki, vstavlennye v grafitovye kapsuly. Nekotorye iz tabletok imeli pogranichnuyu zonu ieh chistogo karbida tsirkoniya, tolshchinoj 1 - 2 mm. Obraztsy pomeshchalis' v pechi ehlektricheskogo soprotivleniya, dayushchie maksimal'nuyu temperaturu 1600{sup o}C. Nejtronnyj potok vo vremya oblucheniya sostavlyal 3 - 4 x 10{sup 10} n/cm{sup 2} -sek. Petlya pozvolyala izmerit' vydelenie izotopov inertnykh gazov Kr{sup 85m}, Kr{sup 87}, Kr{sup 88},Xe{sup 133} i Xe{sup 135} vo vremya oblucheniya, i kosvennoe opredelenie I{sup 133} i I{sup 135} posle vyklyucheniya reaktora. Minimum vydeleniya I{sup 131}, Sr{sup 88}, Ba{sup 141} i Ce{sup 141} byl opredelen radiokhimicheskim metodom posle izvlecheniya obraztsa iz

  7. Combat stiffness of the launcher platform / Боевая устойчивость РСЗО / Borbena žilavost lansirnog sistema

    Directory of Open Access Journals (Sweden)

    Miloš S. Lazarević

    2017-10-01

    osnovu analize opterećenja izrađen je matematičko-mehanički model stabilnosti višecevnog lansera raketa pogođenog u neposrednoj blizini trenutno-fugasnim projektilom. Dobijeni rezultati ukazuju na zavisnost stabilnosti lansera od udaljenosti eksplozije, tipa eksplozije i mase eksplozivnog punjenja. Kao granični uslov borbene žilavosti lansera usvojen je uslov početnog prevrtanja lansera i narušavanja pouzdanog držanja rakete u lansirnoj cevi. Radi uprošćavanja prikazanog modela izvršen je proračun kinetičke energije efikasnog parčeta koje deluje na lanser.

  8. Improved method for lifetime measurements; Methode perfectionnee de mesure de la duree de vie; Usovershenstvovannyj metod izmereniya vremeni zhizni; Metodo perfeccionado para medir la vida media de los estados de excitacion

    Energy Technology Data Exchange (ETDEWEB)

    Weinzierl, P; Bartl, W [Oesterreichische Studiengesellschaft fuer Atomenergie, Seibersdorf (Austria)

    1962-04-15

    entre los dos detectores. El espectro de impulsos del dispositivo sumador se hace incidir sobre un analizador de un solo canal para la seleccion de la energia deseada. El rayo {gamma} (I) se detecta en otro cristal organico. Los impulsos rapidos de ambos detectores organicos pasan a un convertidor tiempo-altura de impulsos y a un analizador multicanal. Este analizador se hace actuar como puerta mediante una coincidencia lenta entre los discriminadores de alturas de impulsos. (author) [Russian] Izmerenie vremeni zhizni yadra v vozbuzhdennom sostoyanii obychno osnovano na izmerenii otstavaniya odnogo gamma-lucha (II) po otnosheniyu k drugomu gamma-luchu (I) ili k beta-chastitse. Organicheskie stsintillyatory dayut nailuchshuyu razreshayushchuyu sposobnost' po vremeni dlya izmereniya vremeni takogo raspada, no dlya slozhnykh protsessov raspada opredelenie gamma-ehnergii predstavlyaet bol'shoe znachenie i mozhet byt' luchshe vsego dostignuto stsintillyatorami s kristallom NaI(Tl). Dlya sovmestnogo ispol'zovaniya preimushchestv detektorov togo i drugogo tipa gamma-luch (II) prezhde vsego rasseivaetsya v organicheskom kristalle (stil'ben), a rasseyannyj kvant detektiruetsya kristallom Nal(Tl). Dlya osushchestvleniya bol'shikh uglov priemki mezhdu dvumya stsintillyatorami izmerenie gamma-ehnergii dostigaetsya posle slozheniya amplitudy oboikh stsintillyatsionnykh impul'sov. Dlya obespecheniya nadezhnogo dejstviya ustanovki dlya slozheniya postupayushchie iz organicheskogo kristalla impul'sy prokhodyat prezhde vsego cherez strobiruyushchuyu skhemu, kotoraya initsiiruetsya sovpadeniem mezhdu dvumya stsintillyatorami. Spektr impul'sov, postupayushchij iz ustanovki dlya slozheniya, napravlyaetsya v odnokanal'nyj analizator dlya otbora po ehnergii. Gamma-luch (I) detektiruetsya v drugom organicheskom kristalle. Bystrye impul'sy oboikh organicheskikh stsintillyatorov napravlyayutsya v amplitudno-vremennoj preobrazovatel' impul'sov i v mnogokanal'nyj analizator. EHtot analizator

  9. Electronic methods for discriminating scintillation shapes; Methodes electroniques de discrimination des formes des impulsions issues de scintillateurs; Ehlektronnye metody diskriminatsii form stsintillyatsii; Metodos electronicos de discriminacion de forma de impulsos de centelleo

    Energy Technology Data Exchange (ETDEWEB)

    Forte, M; Konsta, A; Maranzana, C [European Atomic Energy Community, CCR, ISPRA (Italy)

    1962-04-15

    hasta impulsos debiles, de unas cuantas decenas de fotoelectrones, y la discriminacion de fragmentos emitidos por captura neutronica en liquidos conteniendo boro. Algunas de estas redes fueron capaces de operar con impulsos de la misma polaridad emitidos por dos de los ultimos dinodos, incluso con la salida de un solo electrodo. Ello puede ser util cuando conviene emplear el anodo independientemente, por ejemplo, para sincronizacion. (author) [Russian] Kak uzhe soobshchalos' ran'she, forma stsintillyatsionnogo impul'sa, kharakterizuyushchaya tip vozbuzhdayushchej chastitsy (ehlektron, proton, al'fa i t.d.), mozhet byt' prevrashchena v nezavisimyj ot amplitudy impul'sa parametr. EHto pozvolyaet vyyavit' posredstvom mnogokanal'nogo analizatora sostav vozbuzhdayushchego stsintillyator puchka so smeshannymi chastitsami. EHtot metod byl uspeshno primenen k neskol'kim stsintillyatoram kak organicheskogo, tak i neorganicheskogo tipa. Privodyatsya detali ehlektronnykh metodik, ispol'zovannykh dlya preobrazovaniya formy impul'sov. Dlya bolee prostykh sluchaev diskriminatsii tol'ko mezhdu dvumya vidami impul'sov (naprimer, diskriminatsiya nejtronov ot gamma-izluchenij) rassmatrivalas' takzhe vozmozhnost' ispol'zovaniya passivnykh skhem, predstavlyayushchikhsya perspektivnymi dlya dal'nejshikh usovershenstvovanij i uproshchenij. Bylo isprobovano neskol'ko skhem, glavnym rezul'tatom chego bylo to, chto pri nalichii fona gamma-izlucheniya udalos' rasprostranit' diskriminatsiyu protonov otdachi v zhidkikh stsintillyatorakh na malye impul'sy vsego lish' v neskol'ko desyatkov fotoehlektronov, a takzhe dobit'sya diskriminatsii oskolkov zakhvata nejtronov v soderzhashchikh bor zhidkostyakh. Nekotorye iz ehtikh skhem byli prednaznacheny dlya raboty s impul'sami odinakovoj polyarnosti, podavaemymi dvumya poslednimi ehlektrodami umnozhitelya, ili dazhe s vykhodnymi impul'sami odnogo lish' ehlektroda. EHto mozhet okazat'sya poleznym pri nezavisimom ispol'zovanii anoda, naprimer, dlya

  10. Separation of Impurities in the Zinc Rectification Process by Radioactive Isotopes; Separation des Impuretes, a l'Aide de Radioisotopes, dans l'Affinage du Zinc par Voie Seche; ОТДЕЛЕНИЕ ПРИМЕСЕЙ В ПРОЦЕССЕ РЕКТИФИКАЦИИ ЦИНКА С ПРИМЕНЕНИЕМ РАДИОАКТИВНЫХ РАДИОИЗОТОПОВ; Estudio Mediante Radioisotopos de la Separacion de Impurezas en el Proceso de Purificacion del Cinc

    Energy Technology Data Exchange (ETDEWEB)

    Akerman, K.; Brafman, M.; Fik, H.; Kitala, J.; Nowak, M.; Poczynajlo, A. [Institute of Nuclear Research, Polish Academy of Sciences, Warsaw (Poland)

    1963-03-15

    experiences confirment la theorie elaboree par A. Krupkowski. Elles permettent en outre de formuler des propositions concretes concernant une modification a apporter aux parametres qui traduisent les conditions dans lesquelles s'effectue la condensation des vapeurs zinc-cadmium dans la colonne cadmium. Grace a cette modification, on peut augmenter la recuperation de cadmium provenant du metal primitif, et ameliorer la qualite du zinc de grande purete obtenue par redistillation. (author) [Spanish] En la memoria la separacion de impurezas en el proceso de purificacion del cinc se estudia con ayuda de radioisotopos. Se describen brevemente el proceso de redestilacion del cinc en columnas del tipo New Jersey y sus principios teoricos, establecidos por A. Krupkowski. Se resumen las conclusiones practicas que se desprenden de la expresion matematica del proceso, obtenida basandose en la teoria mencio nada. Se describen asimismo los experimentos de separacion de impurezas de alto y bajo punto de ebullicion presentes en el cinc y el comportamiento del propio componente basico en condiciones normales de trabajo. Estos experimentos se llevaron a cabo utilizando los radioisotopos {sup 64}Cu y {sup 59}Fe (impureza de alto punto de ebullicion), used (impureza de bajo punto de ebullicion) y {sup 69m}Zn (componente basico). Las conclusiones extraidas de los datos experimentales corroboran la teoria de la redestilacion del cinc, elaborada por A. KrupkowskL Ademas, estas conclusiones permiten definir las propuestas que cabe formular con respecto a cambios en los parametros con arreglo a los cuales la condensacion de los vapores de cinc-cadmio se efectua en la columna del cadmio. Estos cambios permiten aumentar la recuperacion de cadmio del metal cargado y mejorar la calidad del cinc de alta pureza, obtenido por redestilacion. (author) [Russian] V rabote korotko opisan process rektifikacii cinka v kolonnah tipa N'ju-Dzhersi i teoreticheskie osnovy jetogo processa, razrabotannye A. Krupkovskim

  11. Experiments on multi-stage light intensification by electro-luminescence; Experiences sur l'intensification de la lumiere en cascade par electroluminescence; Opyty po mnogokaskadnomu svetousileniyu (fotoumnozheniyu) posredstvom ehlektrosvecheniya; Experimentos sobre intensificacion en cascada de la luminosidad por electroluminiscencia

    Energy Technology Data Exchange (ETDEWEB)

    Owaki, K; Nakamura, T [Kobe Kogyo Corporation, Okubo, Akashi, Hyogo (Japan)

    1962-04-15

    S fotosensible en polvo, aglomerado con plastico y moldeado. Basandose en los resultados obtenidos con un solo elemento intensificador, se construyeron intensificadores de dos y tres etapas y se efectuaron experimentos para estudiar sus caracteristicas con diferentes resistencias montadas en paralelo. Con el intensificador de tres etapas se obtuvo una amplificacion del orden de 400, para una radiacion de entrada igual a 0,3 rdlux. Estos resultados sugieren la posibilidad de obtener un mayor aumento para una radiacion de entrada menor. Los autores estiman posible aplicar estos resultados experimentales a los intensificadores solidos de imagenes disenando un dispositivo adecuado. (author) [Russian] Za poslednie gody, v kachestve odnogo iz vazhnykh primenenij ehlektroniki tverdykh tel, byl opublikovan tselyj ryad dokladov otnositel'no povysheniya yarkosti izobrazhenij s pomoshch'yu kristallicheskogo usilitelya. Predstavlyaetsya udobnym i vazhnym ispol'zovat' kristallicheskij usilitel' dlya svetousileniya (fotoumnozheniya). TSel'yu nastoyashchej ehksperimental'noj raboty yavlyaetsya povyshenie stepeni usileniya posredstvom mnogostupenchatogo kaskadirovaniya usilitelya. V nastoyashchem doklade snachala razbirayutsya ehlektricheskie i opticheskie kharakteristiki monokaskadnogo usilitelya, a zatem s tsel'yu uluchsheniya ego parametrov kratko izlagayutsya preimushchestva ispol'zovaniya parallel'nogo soprotivleniya s ehlektro- svetyashchejsya panel'yu. Bylo ispol'zovano dva tipa fotoprovodyashchej yachejki, odna iz kotorykh byla uplotnennaya yachejka iz Cds, a drugaya byla sdelana iz fotochuvstvitel'nogo poroshka Cds, sformovannogo vmeste s plasticheskim svyazyvayushchim veshchestvom. Na osnovanii rezul'tatov, poluchennykh na monokaskadnom usilitele, byli postroeny dvukhkaskadnye i trekhkaskadnye usiliteli, i ikh kharakterisgiki byli provereny dlya razlichnykh parallel'no vklyuchennykh soprotivlenij. Pri pomoshchi trekhkaskadnogo usilitelya bylo polucheno pri vkhodyashchej radiatsii v 0

  12. Electron and Proton Transfer by the Grotthuss Mechanism in Aqueous Solution and in Biological Systems; Transfert d'Electrons et de Protons par le Mecanisme de Grotthuss en Solution Aqueuse et dans les Systemes Biologiques; Perenos ehlektronov i protonov mekhanizmom grotkhusa v vodnom rastvore i v biologicheskikh sistemakh; Transferencia Electronica y Protonica por el Mecanismo de Grotthuss en Soluciones Acuosas y en Sistemas Biologicos

    Energy Technology Data Exchange (ETDEWEB)

    Horne, R. A.; Courant, R. A.; Johnson, D. S. [Arthur D. Little, Inc. Cambridge, MA (United States)

    1965-10-15

    jelektronnogo Fe{sup II} - Fe{sup III} i nekotorye dolgovremennye biologicheskie reakcii okislenija-vosstanovlenija svjazany s perenosom jelek- tronov mehanizmom tipa Grothusa cherez vodjanye mostiki. Mehanizm Grothusa javljaetsja takzhe prichinoj anomal'no bol'shoj jelektroprovodnosti kislotnyh vodnyh rastvorov. Pri obychnyh davlenijah stupen'ju, opredeljajushhej skorost' mehanizma Grothusa, javljaetsja vrashhe- nie N{sub 2}O ili, vozmozhno N{sub 3}O+ , a ne dejstvitel'naja orientacija protonov. Mehanizm Grothusa ogranichivaetsja 'svobodnoj' vrashhajushhejsja monometricheskoj vodoj mezhdu skoplenijami Frank- Vena v zhidkoj vode i izbegaet oblastej otnositel'nogo porjadka. Zavisimost' protonnoj provodimosti ot koncentracii mozhet byt' predstavlena uravneniem, osnovannym na kubicheskom korne jekstrapoljacii koncentracii i soderzhashhim uslovija Arheniusa, pri kotoryh jenergii aktivacii javljajutsja jenergijami dlja vrashhenija i obrazovanija 'otverstij' v rastvorjajushhej vode. Takim obrazom, himicheskuju i jelektricheskuju jenergiju mozhno bystro peredavat' na sravnitel'no bol'shie rasstojanija s pomoshh'ju mehanizma Grothusa. Takie processy svjazany s rjadom javlenij, predstavljajushhih interes dlja biologii, primerami kotoryh javljajutsja myshechnoe sokrashhenie i himija dyhatel'nyh pigmentov. (author)

  13. Protivoklopni vođeni projektili zapadne Evrope, Izraela i Indije / Anti-tank guided missiles of western Europe, Israel and India

    Directory of Open Access Journals (Sweden)

    Goran M. Lazić

    2010-10-01

    Full Text Available Protivoklopni vođeni projektili namenjeni su za uništavanje teško-oklopljenih tenkova, kao i drugih oklopnih vozila. Ovaj rad nudi istorijsko-tehnički pregled (razvoj projektila kroz generacije i osnovni podaci vezani za borbeno-operativno dejstvo ovih projektila ovog tipa naoružanja koje poseduju zemlje zapadne Evrope, Izraela i Indije. Pored osnovnih podataka navode se i cene nekih projektila ponaosob, kao i tendencije razvoja u ovoj grani naoružanja. / Anti-tank guided missiles are designed to hit and destroy heavily armored tanks and other armored fighting vehicles. This review offers a historical and technical overview (development of missiles throughout generations and basic data about combat and operational actions of this type of weapons in Western Europe, Israel and India. The review also offers prices of some missiles and tendencies of development in this branch. Anti-tank guided missiles are primarily designed to destroy armoured tanks as well as other armoured vehicles. Anti-tank guided systems differ in size, from small ones (shoulder-launched missile weapons carried by a single person to complex weapon systems (crewserved, vehicle-mounted and airborne systems. The first generation of anti-tank guided missiles is a manually guided MCLOS (Manual Command to Line of Sight projectile requiring an operator to guide and steer it to a target by a joystick. Vickers vigilant is a British anti-tank wire-guided missile, produced in 1956. The Bantam (Bofors Anti-Tank Missile or Robot 53 (RB 53 is a Swedish anti-tank wire-guided missile, produced in 1963. Cobra is a German - Swiss product which entered the operational use in 1956. It was replaced by Cobra 2000 and Mamaba systems, which are anti-tank guided missiles of the first generation, but with improved guidance and electronics. ENTAC (Engin téléguidé anti-char or MGM Petronor-32A is a French anti-tank wire-guided missile, widely spread and still in the operational use in many

  14. Autofluorography with an X-Ray Image Amplifier; Autofluorographie a l'Aide d'un Amplificateur d'Images a Rayons X; Avtofl u orografiya s pomoshch'yu usilitelya rentgenovskogo izobrazheniya; Autofluorografia con un Amplificador de Imagen de Rayos X

    Energy Technology Data Exchange (ETDEWEB)

    Ter-Pogossian, M. M.; Eichling, J. O. [Washington University School of Medicine, St. Louis, MO (United States)

    1964-10-15

    traitent de l'utilite de ce dispositif pour la visualisation des tumeurs du cerveau, des reins et de la thyroide. (author) [Spanish] La visualizacion de organos que contienen isotopos radiactivos emisores de fotones (rayos X o gamma) de energia comprendida entre 20 y 100 keV aproximadamente, puede lograrse convirtiendo en luz, mediante un amplificador de imagen de rayos X de tipo corriente, la radiacion emitida por el organo. El aparato construido con esta finalidad esta constituido por los siguientes elementos: 1. Un colimador, cuyas caracteristicas vienen determinadas por el poder de resolucion y la distancia a que debe operar. 2. Un amplificador de imagen de rayos X de enfoque electrostatico, que convierte los rayos X o gamma colimados en una imagen optica muy brillante. 3. Un sistema de lentes de gran apertura que proyecta la imagen en la camara mencionada a continuacion. 4. Una camara 'Polaroid' cargada con pelicula rapida (10 000 ASA) de gran contraste. El rendimiento de este aparato para fotones de baja energia es superior al de los exploradores centelleograficos de tipo tradicional. Los autores examinan su utilidad para visualizar tumores cerebrales, renales y tiroideos. (author) [Russian] Vizual'noe nabljudenie organov, soderzhashhih radioaktivnye izotopy, kotorye i z luchajut rentgenovskie kvanty ili gamma-kvanty s jenergijami v predelah ot 20 do 100 kjev, do stiga et sja za schet prevrashhenija radiacii organa v svechenie s pomoshh'ju usilitelja rentgenovskogo izobrazhenija obychnogo tipa. Skonstruirovannyj dlja jetoj celi apparat sostoit iz sledujushhih jelementov: 1 . Kollimatora, harakteristiki kotorogo opredeljajutsja razreshajushhej sposobnost'ju i zh e laemym rabochim rasstojaniem. 2 . Jelektrostaticheskogo fokusirujushhego usilitelja r ent genov skogo izobrazhenija, kotoryj prevrashhaet kollimirovannye rentgenovskie kvanty ili gamma-kvanty v opticheskoe izobrazhenie, imejushhee bol'shuju jarkost'. 3 . Ob{sup e}ktiva s bol'shoj diafragmoj, kotoryj

  15. Regularities in the Changes of Absorber Material Properties as a Function of Absorber Concentration; Regularite des Variations des Proprietes des Substances Absorbantes en Fonction de la Concentration de l'Absorbant; Zakonomernosti izmeneniya svojstv poglashchayushchikh materialov v zavisimosti ot kontsentratsii poglotitelya; Leyes de Variacion de las Propiedades de los Materiales Absorbentes en Funcion de la Concentracion del Absorbente

    Energy Technology Data Exchange (ETDEWEB)

    Portnoj, K. I.

    1964-06-15

    raboty v re akto r ah na teplovyh i promezhutochnyh nejtronah. Pogloshhajushhte materialy, soderzhashhie bor, naprimer boridy,obladajut nizkimi mehanicheskimi svojstvami, chto svjazano s osobennostjami ih kristallicheskoj struktury. M a terialy, soderzhashhie okisly redkozemel'nyh jelementov (samarij, evropij, gadolinij, disprozij idr.), dispergirovannye v matrice iz splava tipa nimonik ili v nerzhavejushhej stali znachitel'no izmenjajut mehanicheskie svojstva v zavisimosti ot koncentracii poglotitelja. Avtory vyskazali gipotezu ob obrazovanii maksimumo pogloshhajushhej sposobnosti pri vzaimnom legirovanii poglotitelej. Jeta gipoteza poluchila dal'nejshee podtverzhdenie opy tami s mnogimi metallicheskimi i nemetallicheskimi pogloshhajushhimi sistemami v reaktorah na teplovyh i promezhutochnyh nejtronah. (author)

  16. Electrical limitations to energy resolution in semiconductor particle detectors; Limitations electriques du pouvoir de resolution en energie des detecteurs a semi-conducteurs; Ehlektricheskie ogranicheniya razreshayushchej sposobnosti po ehnergii v poluprovodnikovykh detektorakh chastits; Limitaciones electricas en la resolucion energetica de detectores de particulas a base de semiconductores

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, W L; Goulding, F S [Lawrence Radiation Laboratory, University of California, Berkeley, CA (United States)

    1962-04-15

    isklyuchitel'no svojstvami massy poluprovodnika, privodyatsya uravneniya, dayushchie teoreticheskie predely shuma pri sovmeshchenii detektorov s usilitelyami. Iz ehtikh uravnenij vidno, chto imeyutsya optimal'naya konstanta vremeni dlya usilitelya i napryazhenie smeshcheniya dlya detektora; pri soblyudenii ehtikh uslovij minimal'nyj shum ne zavisit ot udel'nogo soprotivleniya poluprovodnika. Dokazyvaetsya, chto nailuchshie rezul'taty raboty sistemy detektor-usilitel' zavisyat tol'ko ot ploshchadi detektiruyushchej poverkhnosti, vkhodnoj emkosti (za vychetom emkosti samogo detektora), sroka zhizni naimenee mnogochislennogo iz nositelej v poluprovodnike i ot krutizny vkhodnoj ehlektronnoj lampy usilitelya. Opisyvaetsya novaya konstruktsiya detektora s kol'tsevym ograditel'nym ehlektrodom v kachestve neot{sup e}mlemoj chasti konstruktsii detektora, chto v shirokoj mere ustranyaet shum, vyzyvaemyj poverkhnostnoj utechkoj. Soobshchayutsya ehksperimental'nye rezul'taty opredeleniya utechki detektora i razreshayushchej sposobnosti po ehnergii, khorosho sovpadayushchie s teoreticheskimi dannymi. Teoreticheskij predel shuma, vyrazhennogo v vide polnoj shiriny na polovine maksimuma, lezhit dlya kremnievykh detektorov tipa ''p'' v intervale ot 7 do 10 kev na 1 kv.cm pri 25{sup o}C. (author)

  17. Pulsed-Source Experiments with Multiplying and Non-Multiplying Heavy Water Systems; Experiences a l'Aide de Sources Pulsees sur des Systemes Multiplicateurs et Non Multiplicateurs a Eau Lourde; Ehksperimenty s pul'siruyushchim istochnikom na nerazmnozhayushchikh i razmnozhayushchikh ustrojstvakh s tyazheloj vodoj; Experimentos con Fuentes Pulsadas en Sistemas de Agua Pesada Multiplicadores y No Multiplicadores

    Energy Technology Data Exchange (ETDEWEB)

    Utzinger, E.; Heer, W.; Lutz, H. R. [Swiss Federal Institute for Reactor Research, Wuerenlingen (Switzerland)

    1965-10-15

    {sub 2}O. Los autores comparan los valores experimentales con los parametros de la teoria dedos grupos y examinan seguidamente las limitaciones de esta tecnica. Ademas, midieron directamente, utilizando los datos proporcionados por la 'cola' de neutrones retardados de los impulsos, los valores de la reactividad en sistemas acusadamente subcriticos con p Greater-Than-Or-Equal-To -40 dolares. Estos resultados concuerdan satisfactoriamente con los de las mediciones estaticas. (author) [Russian] Na podkriticheskom ustrojstve MINOR Shvejcarskogo federal'nogo instituta po reaktornym issledovanijam v Wuerenlingen osushhestvlena shirokaja programma izmerenij pri pomoshhi pul'sirujushhego istochnika tipa {sup 3}T(d,n){sup 4}He. Provedeny tri kategorii jeksperimentov dlja izmerenija: a) konstant raspada mgnovennyh nejtronov v estestvennyh i slegka obogashhennyh re- shetkah; b) urovnja reaktivnosti v podkriticheskom sostojanii pri pomoshhi raspada mgnovennyh nejtronov i hvostov zamedlennyh nejtronov v estestvennyh i slegka obogashhennyh reshetkah; i v) anizotropii diffuzionnoj konstanty teplovyh nejtronov v tjazheloj vode s pogruzhen- nym v nee raznym kolichestvom parallel'no raspolozhennyh pustyh trubok raznyh razmerov. Dlja kazhdogo ustrojstva potok teplovyh nejtronov, zavisjashhij ot vremeni, izmerjali v razlichnyh polozhenijah po vysote dlja poluchenija konstant raspada mgnovennyh nejtronov dlja razlichnyh osevyh laplasianov (analiz Fur'e) bez izmenenija vysoty dejstvitel'nogo urovnja tjazheloj vody. Jeksperimental'nye znachenija sravnivajutsja s teoreticheskimi dvu- gruppovymi parametrami. Obsuzhdajutsja nedostatki jetogo metoda. 'dopolnenie k jetomu putem ispol'zovanija hvosta zamedlennyh pul'sirujushhih nejtronov neposredstvennym obra- zom byla izmerena reaktivnost' v sil'no podkriticheskih sistemah s p Greater-Than-Or-Equal-To -40$. Rezul'taty sravnivajutsja so statisticheskimi izmerenijami, i oni dajut ves'ma horoshee sovpadenie. (author)

  18. Radiation-Induced Polymerization of Aldehydes and Ketones; Polymerisation radiochimique des aldehydes et des cetones; Radiatsionnaya polimerizatsiya al'degidov i ketonov; Polimerizacion radioinducida de aldehidos y cetonas

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, K.; Yamaoka, H.; Fujiwara, K.; Sakamoto, M.; Mori, S.; Natori, T.; Yoshida, H.; Okamura, S. [Japanese Association for Radiation Research on Polymers, Neyagawa Osaka (Japan); Kyoto University, Kyoto (Japan)

    1963-11-15

    polimerizatsiyu, keton mozhno prevratit' v polimer poliehfirnogo tipa; esli polimerizatsiya proizvoditsya v tverdom sostoyanii, to poluchaetsya, krome togo, poliketon. Sopolimer ketona s formal'degidom neskol'ko bolee ustojchiv. Dimetilketon mozhno legko polimerizovat' v poliatsetal' kak v zhidkom, tak i v tverdom sostoyanii. Vse ehti tipy polimerizatsii predstavlyayut soboj raznovidnosti vyzyvaemykh oblucheniem reaktsij, kinetika kotorykh predstavlyaet interes. Otdel'nye aspekty ehtoj dannoj problemy rassmatrivayutsya v ehtoj rabote. (author)

  19. Elements of a thermic method of preparing beta-sources with fused carriers, including strontium-90; Elements d'une methode thermique de preparation de sources beta avec des entraineurs fondus, y compris le strontium-90; Osnovy termicheskogo metoda prigotovleniya beta-istochnikov s plavlennymi nositelyami, vklyuchayushchimi strontsij-90; Bases de un metodo termico de preparacion de fuentes beta con portadores fundidos, incluido el estroncio-90

    Energy Technology Data Exchange (ETDEWEB)

    Bogdanov, N I; Zakharova, K P; Zimakov, P V; Kulichenko, V V

    1962-01-15

    avtomaticheskogo kontrolya i regulirovaniya proizvodstvennykh protsessov. Tekhnologicheskij protsess izgotovleniya istochnikov osnovan na obezvozhivanii smesi, sostoyashchej iz radioaktivnogo rastvora azotnokislogo strontsiya i komponentov tipa bornogo angidrida, okisi kremniya, okisi alyuminiya i dr. Termicheskaya obrabotka obezvozhennoj smesi pri vysokoj temperature privodit k obrazovaniyu legkopodvizhnogo rasplava, posle okhlazhdeniya kotorogo poluchaetsya steklovidnaya massa, vklyuchayushchaya v sebya neobkhodimye kolichestva radioizotopa Sr{sup 90}. Privodyatsya dannye i obsuzhdayutsya rezul'taty issledovaniya protsessa obezvozhivaniya sistemy SrO-B{sub 2}O{sub 3}-SiO{sub 2} v intervale temperatur' 100 - 1000{sup o} i obosnovyvaetsya vybor osnovnykh parametrov tekhnologicheskogo protsessa. Izlagayutsya osnovy metoda naneseniya steklovidnogo preparata s neobkhodimym kolichestvom radioizotopa Sr{sup 90} na podlozhki razlichnykh form i razmerov iz stali, keramiki i drugikh materialov. Rassmatrivayutsya osnovnye parametry, kharakterizuyushchie nadezhnost' i bezopasnost' v ehkspluatatsii razlichnykh tipov istochnikov i privodyatsya dannye po istochnikam na osnove Sr{sup 90}, izgotavlivaemym termicheskim metodom. (author)

  20. Preparation of C{sup 14}-labelled tetrazolium salts and tracer study of the tetrazene-formazan rearrangement; Preparation de sels de tetrazolium marques au carbone-14 et etude de la transposition tetrazene-formazan, au moyen d'indicateurs radioactifs; Izgotovlenie mechennykh C{sup 14} solej tetrazosoedinenij i issledovanie pri pomoshchi indikatorov peregruppirovok tetrazona-formazana; Preparacion de sales de tetrazolio marcadas con {sup 14}C y estudio de la transposicion tetraceno-formazan con ayuda de trazadores

    Energy Technology Data Exchange (ETDEWEB)

    Marton, Joseph; Meisel, Julia [Central Research Institute for Chemistry of the Hungarian Academy of Sciences, Budapest (Hungary); Gosztonyi, Thomas [Institute of Organic Chemical Technology, Technical University, Budapest (Hungary)

    1962-03-15

    } solej ditetrazoliya vysokoj chistoty. Obrazovanie formazana, predshestvennika solej tetrazoliya, prokhodit cherez neustojchivuyu promezhutochnuyu stadiyu strukturnogo tipa tetrazona, bystro peregruppiruyushchegosya v shchelochnoj srede, chtoby dat' formazan. V podkhodyashchikh usloviyakh promezhutochnyj tetrazon mozhet byt' otdelen. Ispol'zovanie mechennogo C{sup 14} benzal'degidfenilgidrazoniya pozvolilo issledovat' ehtu peregruppirovku i proverit' ukazyvaemuyu mezhmolekulyarnuyu strukturu. (author)

  1. Economics of Grain Irradiation; Aspects Economiques de l'Irradiation du Grain; Ehkonomika oblucheniya zerna; Aspectos Ecomomicos de la Irradiacion de Granos

    Energy Technology Data Exchange (ETDEWEB)

    Baines, B. D. [Nuclear Chemical Plant Ltd. (United Kingdom); Mosely, J. [Radiation Dynamics Ltd., London (United Kingdom)

    1966-11-15

    podhodjashhim, i te oblasti, v kotoryh nailuchshimi mogut javit'sja predprijatija drugogo tipa v zavisimosti ot uslovij mestoraspolozhenija, uslovij mestnoj tehnologii i metodov obrabotki.; Dva sravnivaemyh predprijatija opisyvajutsja dovol'no podrobno s cel'ju predostavlenija vozmozhnosti tochnogo opredelenija ob{sup e}ma postavok oborudovanija, vhodjashhih v chislo podlezhashhih uchetu rashodov. Ispol'zovannye metody kal'kuljacii byli obsuzhdeny s buhgalterami, rabotajushhimi v oblasti promyshlennosti, s tem, chtoby poluchit' uverennost' v ih priemlemosti dlja potencial'nyh potrebitelej. Ispol'zovannye metody ob{sup j}asneny takim obrazom, chto oni mogut byt' primeneny k problemam analogichnogo haraktera. (author)

  2. Critical Consideration of the Methods of Calculation Used in the Evaluation of the Absorbed Dose to the Skin in Cases of External Contamination; Observations Critiques sur les Methodes de Calcul Utilisees pour l'Evaluacion de la Dose Absorbee par la Peau en Cas de Contamination Externe; 041a 0420 0414 ; Observaciones Criticas Sobre los Metodos de Calculo Utilizados para Evaluar la Dosis Absorbida por la Piel en Caso de Contaminacion Externa

    Energy Technology Data Exchange (ETDEWEB)

    Casnati, E.; Breuer, F. [Gruppo di Dosimetria e Standardizzazione, CNEN, Centro di Studi Nucleari della Casaccia, Rome (Italy)

    1965-06-15

    'ju sravnivajutsja rezul'taty, poluchennye dlja jetogo opredelennogo vida geometrii s pomoshh'ju formuly Rossi i Jellisa i formuly Loevingera dlja beta-chastic. Dlja gamma-izluchenija provoditsja sravnenie velichin, poluchennyh s pomoshh'ju jeksponencial'noj formuly i dvuh drugih analogichnyh formul, prigodnyh dlja uslovij maksimal'nogo i nulevogo nakoplenija fotonov. Rezul'taty pozvoljajut zakljuchit', chto pri imejushhihsja geometricheskih uslovijah kak doza ot beta-izluchenija, tak i doza ot gamma-izluchenija dlja osnovnogo sloja kozhi mozhet opredeljat'sja s pomoshh'ju formuly jeksponencial'nogo tipa. Rezul'taty fakticheski priemlemy takzhe s tochki zrenija ohrany zdorov'ja. (author)

  3. EURATOM's Programme of Participation in Power Reactor Construction; Le programme de participation d'Euratom aux reacteurs de puissance; Programma uchastiya v razrabotke ehnergeticheskikh reaktorov Evratoma; El programa de participacion de la Euratom en la construccion y explotacion de reactores de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ramadier, R. C.; Parker, E. [Communaute Europoenne de l' Energie Atomique, Bruxelles (Belgium)

    1963-10-15

    razrabotke dvukh ehnergeticheskikh reaktorov. Ehti zaprosy byli predstavleny sootvetstvenno Ob''edineniem Rheinisch-Westffllischee Elektrizitfltswerk - Bayernwerke (RWE-BW) N.V. Samenwerkende Electriciteits -Productiebedriyve. Pervyj zapros kasaetsya kipyashchego reaktora s dvojnym tsiklom moshchnost'yu v 237 mgvt ehl), vtoroj - kipyashchego reaktora s pryamym tsiklom i estestvennoj tsirkulyatsiej moshchnost'yu v 50 mgvt (ehl). Sovmestnoe uchastie mozhet prinimat' razlichnye formy. Ono mozhet, v chastnosti, vylit'sya v uchastie pri pokrytii veroyatnogo defitsita pri proizvodstve ehlektroehnergii na ehlektrostantsiyakh v techenie pervykh let ikh ehkspluatatsii. Takoe uchastie Evratoma imelo tsel'yu pooshchrit' stroitel'stvo nekotorykh iz ehtikh atomnykh ehlektrostantsij. K tomu zhe ono pozvolit i v dal'nejshem poluchat' chrezvychajno poleznuyu informatsiyu v posleduyushchie gody, kogda problemy predstoyashchej deyatel'nosti v oblasti razvitiya atomnoj ehnergii vstanut so vsej ochevidnost'yu. (author)

  4. In Vivo and Air Dosimetry of Fission-Spectrum Neutrons; Dosimetrie In Vivo et dans l'Air du Spectre des Neutrons de Fission; Dozimetriya v vozdukhe i dozimetriya In Vivo nejtronov spektra deleniya; Dosimetria In Vivo y en el Aire de Neutrones de un Espectro de Fision

    Energy Technology Data Exchange (ETDEWEB)

    Mobley, T. S.; Engel, R. E.; Godden, W. R. [Kirtland Airforce Base, New Mexico (United States); Penikas, V. T. [AFIT, Wright-Patterson Air Force Base, Ohio, with Duty Station at University of Rochester, School of Medicine and Dentistry, Rochester, NY (United States)

    1964-03-15

    bornogo sharika, soderzhashhego kadmij i pokrytogo fol'goj poroga delenija (Pu, Np, U), sernoj tabletki i treh tipov dozimetrov, primenjavshihsja v podkozhnom detektore. Dozimetricheskij pribor pomeshali v brjushnoj polosti podopytnyh zhivotnyh za vosemnadcat' chasov do obluchenija, prikrepljaja e go k perednej storone rubcevogo otdela zheludka. Opisyvaetsja metod rassechenija rubcevogo otdela zheludka. Doza nejtronov izmerjalas' s pomoshh'ju porogovyh izmerenij fol'gi. Zoloto i zoloto, pokrytoe kadmiem, ispol'zovalis' dlja opredelenija integrirovannogo potoka teplovyh nejtronov; plutonij-239, neptunij-237, uran-238 i sera-32 - dlja opredelenija integrirovannyh potokov bystryh nejtronov; radiofotoljuminiscentnye stekljannye sterzhni - dlja opredelenija dozy gamma-luchej. Ovcu podvergali oblucheniju sboku na rasstojanii (po srednej linii) 200 cm, ili 175 sm ot centra kriticheskoj sborki. Doza nejtronov v radah, izmerennaja v vozduhe na rasstojanii 200 sm sostavljala 161 {+-}5,5 rada; na rasstojanii 175 sm - 242 {+-} 16,6 rada. Doza gamma-luchej na sootvetstvujushhih rasstojanijah so stavljala 3 3 {+-}2 ,4 i 4 2 {+-}2 ,5 rentgena. Dozy na vhode i vyhode, a takzhe doza vo vnutrennem detektore kolebalas' v svjazi s vnezapnym pod{sup e}mom temperatury, uvelicheniem rasstojanija ot reaktora, polozheniem fol'gi v otnoshenii reaktora i zavisela ot tolshhiny i sostava oslabljajushhih dozu tkanej. (author)

  5. Integral physics data for fast-reactor design; Donnees de physique integrale intervenant dans les etudes de reacteur a neutrons rapides; Integral'nye fizicheskie dannye dlya raschetov reaktorov na bystrykh nejtronakh; Datos fisicos integrales para el diseno de reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Loewenstein, W B; Meneghetti, D [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    dannye po fakticheskim ehnergeticheskim reaktoram-razmnozhitelya m na bystrykh nejtronakh. EHti sistemy slishkom slozhny dlya prove- deniya prostogo teoreticheskogo analiza. Oni svidetel'stvuyut o slozhnosti fakticheskogo reaktora po sravneniyu s bolee idealizirovanny m i legko analiziruemym kriticheskim opytom. Integral'nye fizicheskie dannye dlya rascheta reaktora polucheny v rezul'tate provedennykh na reaktornykh sistemakh kriticheskikh ili nekriticheskikh izmerenij, razlichnykh velichin reaktornoj fiziki, imeyushchikh prakticheskoe j teoreticheskoe znacheniya, ili to ili drugoe znachenie. Oni kharakterizuyut i pozvolyayut ponyat' sistemu. Dany izmereniya kriticheskoj massy, koehffitsienta formy aktivnoj zony, koehffitsientov detektorov, spektrov nejtronov, opytov s zamenoj materiala, otrazhatel'noj dobavki, vremeni zhizni nejtronov, Rossi-{alpha} i podobnykh kharakteristik i velichin. V doklade rassmatrivayuts ya ehti dannye i opisyvayutsya oblasti ikh primeneniya. Pokazano, chto sushchestvuyut ogranicheniya i v ehksperimental'ny kh i v analiticheskikh rezultatakh pri analizakh spektra i kritichnosti sistemy. Dany nametki budushchikh ehksperimental'ny kh i analiticheskikh issledovanij. Ehti issledovaniya pomogut umen'shit' razryv mezhdu teoriej i opytom dlya 'izvestnykh' sistem. Namechayutsya takzhe issledovaniya po 'podkrepleniyu' dannykh fiziki krupnykh ehnergeticheskikh reaktorov-razmnozhitelej na bystrykh nejtronakh. (author)

  6. Shippingport Atomic Power Station Operating Experience, Developments and Future Plans; La centrale nucleaire de Shippingport, experience de son fonctionnement et plans pour l'avenir; Shippingportskaya atomnaya ehlektrostan