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Sample records for sborok reaktora na

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

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

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    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

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

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    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.

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

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    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)

  5. 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

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    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

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

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    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.

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

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    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

  8. 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

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    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.

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

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    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)

  10. 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

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    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.

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

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    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)

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

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    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.

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

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    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.

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

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    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.

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

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    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.

  16. 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.

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. 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

  2. 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.

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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)

  8. 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

  9. 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)

  10. 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.

  11. 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)

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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

  17. 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.

  18. 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.

  19. 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

    obsuzhdenii programm ob{sup j}asnjajutsja obstojatel'stva, vlijajushhie na vybor jeksponen- cial'nyh i chisto kriticheskih sborok, maketov ustanovok nulevoj moshhnosti i jeksperimen- tov na samom reaktore dlja poluchenija neobhodimyh dannyh, a takzhe ta rol', kotoruju igrajut vspomogatel'nye analiticheskie raboty. Na konkretnyh primerah pokazyvaetsja, kakie mo- gut byt' polucheny dannye do nachala raboty reaktora na moshhnosti. Jeti dannye vkljuchajut ostatochnuju reaktivnost' vykljuchennogo reaktora, zapas reaktivnosti dlja jekspluatacionnyh nuzhd, temperaturnye kojefficienty, jeffektivnost' regulirujushhih i avarijnyh sterzhnej, kinetiku reaktora, harakteristiki proizvodstva jenergii, trebovanija v otnoshenii puskovogo istochnika i chuvstvitel'nosti priborov, trebovanija v otnoshenii zashhity i balans nejtro- nov . V obzore nedavnih jeksperimentov v reaktorah nulevoj moshhnosti vyjavljaetsja bol'shaja rol', kotoruju igrajut v poslednee vremja jeksponencial'nye i kriticheskie sistemy v vypol- nenii Argonskoj laboratoriej zadach po razrabotke konstrukcij reaktorov. Ih rol' v budu- shhem vidna iz kratkogo izlozhenija osushhestvljaemyh i zaplanirovannyh programm dlja sem'i dejstvujushhih reaktorov nulevoj moshhnosti Argonskoj laboratorii i ozhidaemogo popolnenija. (author)

  20. 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

  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. 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.

  3. 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.

  4. 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.

  5. 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

  6. 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.

  7. 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

  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. 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

  10. 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

  11. 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)

  12. 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

  13. 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.

  14. 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

  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. 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.

  17. 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

  18. 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.

  19. 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.

  20. 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)

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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)

  6. 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.

  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. 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.

  9. 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

    godine, koja ima za cilj pripremanje materijala i dokumentacije za valjano odlucivanje o buducem statusu reaktora RA. U ovoj godini aktivnost je bila usmerena pre svega na detaljnu analizu stanja u bazenima za odlezavanje isluzenih gorivnih elemenata i pripremu podloga za donosenje valjane odluke o nacinu sanacije stanja u bazenima. Zakljuceno je da nije bilo akcidenata koji bi imali za posledicu znacajniju kontaminaciju radnih povrsina i opreme, kao ni kontaminaciju i ozracivanje osoblja.

  10. 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.

  11. 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.

  12. 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

    podaci o nivoima neutronskog i gama zracenja na karakteristicnim kontrolnim mestima, kao i statisticki pregled ukupnog broja merenja. Dati su takodje rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela radnog osoblja. U drugom delu rada izlozena je analiza ozracivanja radnog osoblja. Konstatovano je da je maksimalna individualna doza spoljasnjeg ozracivanja bila 2,13R, a da je kod 90% ozracivanih doza bila manja od 1/5 maksimalno dopustene godisnje doze. Takodje je ocenjeno, na osnovu ucestanosti poslova u kontaminiranim zonama, preduzimanih kontrolnih i zastitnih mera, kao i procene ocekivane interne kontaminacije, da se moze zanemariti unutrasnje ozracivanje u odnosu na spoljasnje. Dati su takodje, uporedni podaci o ozracivanju osoblja u proteklih pet godina, iz kojih se moze videti da je ozracivanje u protekloj godini bilo manje nego u prethodnim. U trecem delu rada navedeni su numericki podaci i kolicinama sakupljenog radioaktivnog otpadnog materijala, ukupnoj velicini kontaminiranih odnosno dekontaminiranih povrsina i broju dekontaminiranih predmeta. Na kraju data je kratka analiza akcidenata koji su se u toku godine odigrali kod reaktora u procesu standardnog pogona, odnosno poslova odrzavanja i remonta. Maksimalna individualna doza ozracivanja iznosila je 1,4R, a kontaminacija otkrivenih delova tela, oko 6 MDNK (MDNK - maksimalno dozvoljeni nivo kontaminacije)

  13. 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

  14. 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

  15. 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.

  16. 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)

  17. 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.

  18. 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.

  19. 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

    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 godine, koja ima za cilj pripremanje materijala i dokumentacije za valjano odlucivanje o buducem statusu reaktora RA. U ovoj godini aktivnost je bila usmerena pre svega na detaljnu analizu stanja u bazenima za odlezavanje isluzenih gorivnih elemenata i pripremu podloga za donosenje valjane odluke o nacinu snacije stanja u bazenima. Posle opseznih priprema, usvajanja tehnoloskih procedura i nabavke neophodne opreme, u septembru 1997. zapoceta je prva faza snacije bazena - ciscenje mulja sa dna. Zakljuceno je da nije bilo akcidenata koji bi imali za posledicu znacajniju kontaminaciju radnih povrsina i opreme, kao ni kontaminaciju i ozracivanje osoblja.

  20. 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.

  1. 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'.

  2. 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.

  3. 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

  4. 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

  5. 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.

  6. 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)

  7. 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.

  8. 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)

  9. 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.

  10. 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)

  11. 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}.

  12. 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)

  13. 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.

  14. 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.

  15. 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)

  16. 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

  17. 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)

  18. 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.

  19. 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.

  20. 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

  1. 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

  2. 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

  3. 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.

  4. 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)

  5. 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

  6. 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}.

  7. 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

    debido a un control deficiente de los combustibles nucleares y a la falta de precision en las operaciones contables. La administracion de materiales nucleares requiere que los explotadores de los reactores de potencia lleven una contabilidad completa y detallada. No es necesario que los documentos sean complejos si lo que se pretende es que sean completos y adecuados. En realidad, la sencillez es sobremanera conveniente. A pesar de que el combustible nuclear es un combustible nuevo y totalmente distinto de los de tipo tradicional, no hay que rodear su utilizacion de ninguna aureola de misterio. El control de los materiales nucleares no es una simple labor de inventario, sino que constituye la base de muchas otras operaciones inherentes a la explotacion de los reactores de potencia, por ejemplo: el transporte del combustible irradiado, su regeneracion con la correspondiente contabilizacion del combustible recuperado y del material producido durante el funcionamiento del reactor, y, por ultimo, el establecimiento de un sistema de seguros adecuado. (author) [Russian] Otnositel'no novoe i chrezvychajno cennoe toplivo dlja proizvodstva jelektrojenergii, a imenno uran, trebuet ochen' tshhatel'nogo ucheta s momenta, kogda operator reaktora prinimaet na sebja material'nuju otvetstvennost' za jetot material, i do togo momenta, kogda jetot material v vide chastichno otrabotannogo topliva peredaetsja na druguju ustanovku, gde regeneriruetsja ostavshajasja chast' ego pervonachal'noj cennosti. Bol'shaja chast' operatorov jenergeticheskih reaktorov, do pojavlenija v svet jadernoj jenergetiki, rabotala na jelektrostancijah s obychnym iskopaemym toplivom i /zhe davno vyrabotala dostatochno polnye i nadezhnye formy kontrolja za ego rashodovaniem. Operator reaktora dolzhen raspolagat' ne menee nadezhnymi sposobami ucheta jadernyh materialov, ispol'zuemyh na ego ustanovke. Jekspluatacija jenergeticheskih reaktorov ne imeet bol'shoj istorii, i na protjazhenii otnositel'no korotkogo perioda

  8. 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

  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. 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.

  11. 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.

  12. 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)

  13. 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.

  14. 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

  15. 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.

  16. 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.

  17. 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)

  18. 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.

  19. 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

  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. 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.

  2. 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.

  3. 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

  4. 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.

  5. 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

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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

  12. 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)

  13. 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)

  14. 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

  15. 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)

  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. 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

    eksperimentima koji su obavljani. Odstupanja od plana bilo je u maju usled posebnih zahteva korisnika. Ukupni broj prekida rada bio je manji je svih prethodnih godina, uglavnom zbog najavljenih prekida napajanja elekticnom energijom. 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. Kraci prekid rada (kraci od 24 sata) je bio usled vadjenja kapsule UO{sub 2}a koja je bila postavljena u jezgro radi merenja prelaza toplote. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Dogodio se jedan akcident kontaminacije gasovima i aerosolima i to kratkozivecim izotopima. Dekontaminirano je znatno manje povrsina nego ranijih godina. Prakticno i nije bilo kontaminacije povrsina koje bi zahtevale intervencije ekipe za dekontaminaciju osim standardnih dekontaminacija posle izmene goriva. Zakljuceno je da uspesan rad reaktora u 1972. godini ima poseban znacaj kada se ima na umu kriza finansiranja izazvana neblagovremenim resavanjem statusa reaktora. U planu za sledecu godinu naglasava se potreba pravljenja dugorocnog plana koriscenja reaktora. Neophodno je izvrsiti i pripreme za prelazak na rad sa visokoobogacenim gorivom u 1974. godini, kao i realizacija projekta sistema za udesno hladjenja jezgra u slucaju isticanja teske vode, odnosno sprecavanje maksimalnog moguceg akcidenta.

  18. 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.

  19. 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

  20. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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

  14. 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.

  15. Parametri za procena na kvalitetot na polietilenska i na polipropilenska ambalaza i na gumeni zatvoraci nameneti za farmacevtski preparati

    Directory of Open Access Journals (Sweden)

    Liljana Ugrinova

    2002-03-01

    Full Text Available Napraven e pregled na parametrite za procena na kvalitetot na polietilenska i na polipropilenska ambalaza i na gumeni zatvoraci nameneti za farmacevtski preparati. Za procena na kvalitetot na ispituvaniot materijal bea izvrseni fizicki, hemiski i bioloski ispituvanja spored postapkite dadeni vo Ph. Eur., DIN i spored DIN ISO standardite. Baranjata za kvalitet na ovoj vid ambalaza propisani spored Ph. Eur., DIN i DIN ISO standardite se razlikuvaat vo odnos na predvidenite parametri za fizicki, za hemiski i za bioloski ispituvanja. Isto taka, propisani se i razlicni granici na dozvoleno otstapuvanje na oddelni parametri.

  16. 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

  17. 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

  18. Načrtovan porod na domu

    OpenAIRE

    Todorović, Tamara; Takač, Iztok

    2017-01-01

    Izhodišča: Porod na domu je sicer star toliko kot človeštvo, pa vendar v veliki večini srednje in visoko razvitih držav prevladuje mnenje, da so zaradi nepredvidljivosti zapletov porodnišnice najbolj varno okolje za rojevanje. Kljub temu obstaja peščica držav, v katerih je porod na domu integriran v sistem zdravstvenega varstva (npr. Nizozemska, Velika Britanija, Kanada). Pri porodih na domu ločimo nenačrtovane in načrtovane porode na domu, slednje pa lahko nadalje razdelimo še na porode s sp...

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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

  4. Na+-stimulated ATPase of alkaliphilic halotolerant cyanobacterium Aphanothece halophytica translocates Na+ into proteoliposomes via Na+ uniport mechanism

    Directory of Open Access Journals (Sweden)

    Soontharapirakkul Kanteera

    2010-08-01

    Full Text Available Abstract Background When cells are exposed to high salinity conditions, they develop a mechanism to extrude excess Na+ from cells to maintain the cytoplasmic Na+ concentration. Until now, the ATPase involved in Na+ transport in cyanobacteria has not been characterized. Here, the characterization of ATPase and its role in Na+ transport of alkaliphilic halotolerant Aphanothece halophytica were investigated to understand the survival mechanism of A. halophytica under high salinity conditions. Results The purified enzyme catalyzed the hydrolysis of ATP in the presence of Na+ but not K+, Li+ and Ca2+. The apparent Km values for Na+ and ATP were 2.0 and 1.2 mM, respectively. The enzyme is likely the F1F0-ATPase based on the usual subunit pattern and the protection against N,N'-dicyclohexylcarbodiimide inhibition of ATPase activity by Na+ in a pH-dependent manner. Proteoliposomes reconstituted with the purified enzyme could take up Na+ upon the addition of ATP. The apparent Km values for this uptake were 3.3 and 0.5 mM for Na+ and ATP, respectively. The mechanism of Na+ transport mediated by Na+-stimulated ATPase in A. halophytica was revealed. Using acridine orange as a probe, alkalization of the lumen of proteoliposomes reconstituted with Na+-stimulated ATPase was observed upon the addition of ATP with Na+ but not with K+, Li+ and Ca2+. The Na+- and ATP-dependent alkalization of the proteoliposome lumen was stimulated by carbonyl cyanide m - chlorophenylhydrazone (CCCP but was inhibited by a permeant anion nitrate. The proteoliposomes showed both ATPase activity and ATP-dependent Na+ uptake activity. The uptake of Na+ was enhanced by CCCP and nitrate. On the other hand, both CCCP and nitrate were shown to dissipate the preformed electric potential generated by Na+-stimulated ATPase of the proteoliposomes. Conclusion The data demonstrate that Na+-stimulated ATPase from A. halophytica, a likely member of F-type ATPase, functions as an electrogenic Na

  5. Polarization dependence of Na* + Na* associative ionization revisited

    NARCIS (Netherlands)

    Meijer, H.A.J.; Meulen, H.P. v.d.; Morgenstern, R.; Hertel, I.V.; Meyer, E.; Witte, R.

    1986-01-01

    The dependence of the associative ionization process Na 3 2P3/2 + Na 3 2P3/2 → Na2+ + e- on the polarization of the laser light used for Na excitation was independently investigated in Utrecht and Berlin. The purpose of this paper is to clarify discrepancies between two other earlier experimental

  6. 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.

  7. 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)

  8. Pseudo-ternary phase diagram in the Na2O-Na2O2-NaOH system

    International Nuclear Information System (INIS)

    Saito, Jun-ichi; Tendo, Masayuki; Aoto, Kazumi

    1997-10-01

    Generally, the phase diagrams are always used to understand the present state of compounds at certain temperature. In order to understand the corrosion behavior of structural material for FBR by main sodium compounds (Na 2 O, Na 2 O 2 and NaOH), it is very important to comprehend the phase diagrams of their compounds. However, only Na 2 O-NaOH pseudo-binary phase diagram had been investigated previously in this system. There is no study of other pseudo-binary or ternary phase diagrams in the Na 2 O-Na 2 O 2 -NaOH system. In this study, in order to clarify the present states of their compounds at certain temperatures, the pseudo-binary and ternary phase diagrams in the Na 2 O-Na 2 O 2 -NaOH system were prepared. A series of thermal analyses with binary and ternary component system has been carried out using the differential scanning calorimetry (DSC). The liquidus temperature and ternary eutectic temperatures were confirmed by these measurements. The beneficial indications for constructing phase diagrams were obtained from these experiments. On the basis of these results, the interaction parameters between compounds which were utilized for the Thermo-Calc calculation were optimized. Thermo-Calc is one of thermodynamic calculation software. Consequently the accurate pseudo-binary and ternary phase diagrams were indicated using the optimized parameters. (author)

  9. Extracellular Na+ levels regulate formation and activity of the NaX/alpha1-Na+/K+-ATPase complex in neuronal cells.

    Directory of Open Access Journals (Sweden)

    Emmanuelle eBerret

    2014-12-01

    Full Text Available MnPO neurons play a critical role in hydromineral homeostasis regulation by acting as sensors of extracellular sodium concentration ([Na+]out. The mechanism underlying Na+-sensing involves Na+-flow through the NaX channel, directly regulated by the Na+/K+-ATPase α1-isoform which controls Na+-influx by modulating channel permeability. Together, these two partners form a complex involved in the regulation of intracellular sodium ([Na+]in. Here we aim to determine whether environmental changes in Na+ could actively modulate the NaX/Na+/K+-ATPase complex activity.We investigated the complex activity using patch-clamp recordings from rat MnPO neurons and Neuro2a cells. When the rats were fed with a high-salt-diet, or the [Na+] in the culture medium was increased, the activity of the complex was up-regulated. In contrast, drop in environmental [Na+] decreased the activity of the complex. Interestingly under hypernatremic condition, the colocalization rate and protein level of both partners were up-regulated. Under hyponatremic condition, only NaX protein expression was increased and the level of NaX/Na+/K+-ATPase remained unaltered. This unbalance between NaX and Na+/K+-ATPase pump proportion would induce a bigger portion of Na+/K+-ATPase-control-free NaX channel. Thus we suggest that hypernatremic environment increases NaX/Na+/K+-ATPase α1-isoform activity by increasing the number of both partners and their colocalization rate, whereas hyponatremic environment down-regulates complex activity via a decrease in the relative number of NaX channels controlled by the pump.

  10. A Study of the Distribution of Sodium Cations in the Zeolites NaX, NaY and ZnNaY Using Carbon Monoxide Adsorption and 23Na NMR Techniques

    Science.gov (United States)

    Seidel, A.; Boddenberg, B.

    1995-03-01

    The zeolites NaX, NaY, Zn(55)NaY, and Zn(74)NaY were investigated by means of carbon monoxide adsorption and with static and magic angle spinning (MAS) 23Na NMR spectroscopy. The Na+ distribution between the sodalite (ß)- and supercages of the fully hydrated zeolites NaX and NaY were found to agree with XRD results. In the hydrated zinc-exchanged zeolites the Na+ ions almost exclusively populate the ß-cages. The adsorption isotherms of CO in the dehydrated zeolites were analyzed quantitatively to yield the concentrations of Na+ residing in the supercages. The measured static and MAS 23Na NMR spectra were analyzed by comparing their widths and shapes with simulated central transition patterns and yield, inter alia, the concentrations of Na+ associated with the spectrum components. Arguments are put forward that 23Na NMR of dehydrated zeolites is well suited to distinguish Na+ cations in highly symmetric environments and mobile Na+ species from others located on general positions, but further resolution is hardly feasible.

  11. HCO3(-)-coupled Na+ influx is a major determinant of Na+ turnover and Na+/K+ pump activity in rat hepatocytes

    International Nuclear Information System (INIS)

    Fitz, J.G.; Lidofsky, S.D.; Weisiger, R.A.; Xie, M.H.; Cochran, M.; Grotmol, T.; Scharschmidt, B.F.

    1991-01-01

    Recent studies in hepatocytes indicate that Na(+)-coupled HCO3- transport contributes importantly to regulation of intracellular pH and membrane HCO3- transport. However, the direction of net coupled Na+ and HCO3- movement and the effect of HCO3- on Na+ turnover and Na+/K+ pump activity are not known. In these studies, the effect of HCO3- on Na+ influx and turnover were measured in primary rat hepatocyte cultures with 22Na+, and [Na+]i was measured in single hepatocytes using the Na(+)-sensitive fluorochrome SBFI. Na+/K+ pump activity was measured in intact perfused rat liver and hepatocyte monolayers as Na(+)-dependent or ouabain-suppressible 86Rb uptake, and was measured in single hepatocytes as the effect of transient pump inhibition by removal of extracellular K+ on membrane potential difference (PD) and [Na+]i. In hepatocyte monolayers, HCO3- increased 22Na+ entry and turnover rates by 50-65%, without measurably altering 22Na+ pool size or cell volume, and HCO3- also increased Na+/K+ pump activity by 70%. In single cells, exposure to HCO3- produced an abrupt and sustained rise in [Na+]i from approximately 8 to 12 mM. Na+/K+ pump activity assessed in single cells by PD excursions during transient K+ removal increased congruent to 2.5-fold in the presence of HCO3-, and the rise in [Na+]i produced by inhibition of the Na+/K+ pump was similarly increased congruent to 2.5-fold in the presence of HCO3-. In intact perfused rat liver, HCO3- increased both Na+/K+ pump activity and O2 consumption. These findings indicate that, in hepatocytes, net coupled Na+ and HCO3- movement is inward and represents a major determinant of Na+ influx and Na+/K+ pump activity. About half of hepatic Na+/K+ pump activity appears dedicated to recycling Na+ entering in conjunction with HCO3- to maintain [Na+]i within the physiologic range

  12. The effect of Na vapor on the Na content of chondrules

    Science.gov (United States)

    Lewis, R. Dean; Lofgren, Gary E.; Franzen, Hugo F.; Windom, Kenneth E.

    1993-01-01

    Chondrules contain higher concentrations of volatiles (Na) than expected for melt droplets in the solar nebula. Recent studies have proposed that chondrules may have formed under non-canonical nebular conditions such as in particle/gas-rich clumps. Such chondrule formation areas may have contained significant Na vapor. To test the hypothesis of whether a Na-rich vapor would minimize Na volatilization reaction rates in a chondrule analog and maintain the Na value of the melt, experiments were designed where a Na-rich vapor could be maintained around the sample. A starting material with a melting point lower that typical chondrules was required to keep the logistics of working with Na volatilization from NaCl within the realm of feasibility. The Knippa basalt, a MgO-rich alkali olivine basalt with a melting temperature of 1325 +/- 5 C and a Na2O content of 3.05 wt%, was used as the chondrule analog. Experiments were conducted in a 1 atm, gas-mixing furnace with the fO2 controlled by a CO/CO2 gas mixture and fixed at the I-W buffer curve. To determine the extent of Na loss from the sample, initial experiments were conducted at high temperatures (1300 C - 1350 C) for duration of up to 72 h without a Na-rich vapor present. Almost all (up to 98%) Na was volatilized in runs of 72 h. Subsequent trials were conducted at 1330 C for 16 h in the presence of a Na-rich vapor, supplied by a NaCl-filled crucible placed in the bottom of the furnace. Succeeding Knudsen cell weight-loss mass-spectrometry analysis of NaCl determined the P(sub Na) for these experimental conditions to be in the 10(exp -6) atm range. This value is considered high for nebula conditions but is still plausible for non-canonical environments. In these trials the Na2O content of the glass was maintained or in some cases increased; Na2O values ranged from 2.62% wt to 4.37% wt. The Na content of chondrules may be controlled by the Na vapor pressure in the chondrule formation region. Most heating events capable

  13. Na/K pump inactivation, subsarcolemmal Na measurements, and cytoplasmic ion turnover kinetics contradict restricted Na spaces in murine cardiac myocytes.

    Science.gov (United States)

    Lu, Fang-Min; Hilgemann, Donald W

    2017-07-03

    Decades ago, it was proposed that Na transport in cardiac myocytes is modulated by large changes in cytoplasmic Na concentration within restricted subsarcolemmal spaces. Here, we probe this hypothesis for Na/K pumps by generating constitutive transsarcolemmal Na flux with the Na channel opener veratridine in whole-cell patch-clamp recordings. Using 25 mM Na in the patch pipette, pump currents decay strongly during continuous activation by extracellular K (τ, ∼2 s). In contradiction to depletion hypotheses, the decay becomes stronger when pump currents are decreased by hyperpolarization. Na channel currents are nearly unchanged by pump activity in these conditions, and conversely, continuous Na currents up to 0.5 nA in magnitude have negligible effects on pump currents. These outcomes are even more pronounced using 50 mM Li as a cytoplasmic Na congener. Thus, the Na/K pump current decay reflects mostly an inactivation mechanism that immobilizes Na/K pump charge movements, not cytoplasmic Na depletion. When channel currents are increased beyond 1 nA, models with unrestricted subsarcolemmal diffusion accurately predict current decay (τ ∼15 s) and reversal potential shifts observed for Na, Li, and K currents through Na channels opened by veratridine, as well as for Na, K, Cs, Li, and Cl currents recorded in nystatin-permeabilized myocytes. Ion concentrations in the pipette tip (i.e., access conductance) track without appreciable delay the current changes caused by sarcolemmal ion flux. Importantly, cytoplasmic mixing volumes, calculated from current decay kinetics, increase and decrease as expected with osmolarity changes (τ >30 s). Na/K pump current run-down over 20 min reflects a failure of pumps to recover from inactivation. Simulations reveal that pump inactivation coupled with Na-activated recovery enhances the rapidity and effectivity of Na homeostasis in cardiac myocytes. In conclusion, an autoregulatory mechanism enhances cardiac Na/K pump activity when

  14. Na+/Ca2+ exchange and Na+/K+-ATPase in the heart

    Science.gov (United States)

    Shattock, Michael J; Ottolia, Michela; Bers, Donald M; Blaustein, Mordecai P; Boguslavskyi, Andrii; Bossuyt, Julie; Bridge, John H B; Chen-Izu, Ye; Clancy, Colleen E; Edwards, Andrew; Goldhaber, Joshua; Kaplan, Jack; Lingrel, Jerry B; Pavlovic, Davor; Philipson, Kenneth; Sipido, Karin R; Xie, Zi-Jian

    2015-01-01

    This paper is the third in a series of reviews published in this issue resulting from the University of California Davis Cardiovascular Symposium 2014: Systems approach to understanding cardiac excitation–contraction coupling and arrhythmias: Na+ channel and Na+ transport. The goal of the symposium was to bring together experts in the field to discuss points of consensus and controversy on the topic of sodium in the heart. The present review focuses on cardiac Na+/Ca2+ exchange (NCX) and Na+/K+-ATPase (NKA). While the relevance of Ca2+ homeostasis in cardiac function has been extensively investigated, the role of Na+ regulation in shaping heart function is often overlooked. Small changes in the cytoplasmic Na+ content have multiple effects on the heart by influencing intracellular Ca2+ and pH levels thereby modulating heart contractility. Therefore it is essential for heart cells to maintain Na+ homeostasis. Among the proteins that accomplish this task are the Na+/Ca2+ exchanger (NCX) and the Na+/K+ pump (NKA). By transporting three Na+ ions into the cytoplasm in exchange for one Ca2+ moved out, NCX is one of the main Na+ influx mechanisms in cardiomyocytes. Acting in the opposite direction, NKA moves Na+ ions from the cytoplasm to the extracellular space against their gradient by utilizing the energy released from ATP hydrolysis. A fine balance between these two processes controls the net amount of intracellular Na+ and aberrations in either of these two systems can have a large impact on cardiac contractility. Due to the relevant role of these two proteins in Na+ homeostasis, the emphasis of this review is on recent developments regarding the cardiac Na+/Ca2+ exchanger (NCX1) and Na+/K+ pump and the controversies that still persist in the field. PMID:25772291

  15. 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)

  16. 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

  17. Altered Na+ transport after an intracellular alpha-subunit deletion reveals strict external sequential release of Na+ from the Na/K pump.

    Science.gov (United States)

    Yaragatupalli, Siddhartha; Olivera, J Fernando; Gatto, Craig; Artigas, Pablo

    2009-09-08

    The Na/K pump actively exports 3 Na(+) in exchange for 2 K(+) across the plasmalemma of animal cells. As in other P-type ATPases, pump function is more effective when the relative affinity for transported ions is altered as the ion binding sites alternate between opposite sides of the membrane. Deletion of the five C-terminal residues from the alpha-subunit diminishes internal Na(+) (Na(i)(+)) affinity approximately 25-fold [Morth et al. (2007) Nature 450:1043-1049]. Because external Na(+) (Na(o)(+)) binding is voltage-dependent, we studied the reactions involving this process by using two-electrode and inside-out patch voltage clamp in normal and truncated (DeltaKESYY) Xenopus-alpha1 pumps expressed in oocytes. We observed that DeltaKESYY (i) decreased both Na(o)(+) and Na(i)(+) apparent affinities in the absence of K(o)(+), and (ii) did not affect apparent Na(o)(+) affinity at high K(o)(+). These results support a model of strict sequential external release of Na(+) ions, where the Na(+)-exclusive site releases Na(+) before the sites shared with K(+) and the DeltaKESYY deletion only reduces Na(o)(+) affinity at the shared sites. Moreover, at nonsaturating K(o)(+), DeltaKESYY induced an inward flow of Na(+) through Na/K pumps at negative potentials. Guanidinium(+) can also permeate truncated pumps, whereas N-methyl-D-glucamine cannot. Because guanidinium(o)(+) can also traverse normal Na/K pumps in the absence of both Na(o)(+) and K(o)(+) and can also inhibit Na/K pump currents in a Na(+)-like voltage-dependent manner, we conclude that the normal pathway transited by the first externally released Na(+) is large enough to accommodate guanidinium(+).

  18. Active transport of Na+ by reconstituted Na,K-ATPase

    International Nuclear Information System (INIS)

    Boldyrev, A.A.; Svinukhova, I.A.

    1987-01-01

    The ability of ATP, CTP, ITP, GTP, and UTP to support ouabain-sensitive accumulation of Na + by proteoliposomes with a reconstituted Na/K-pump was investigated. At a low [Na + ]/[K + ] ratio in the medium (20 mM/50 mM), a correlation is observed between the proton-accepting capacity of the nucleotide and its effectiveness as a substrate of active transport. To test the hypothesis of the importance of the presence of a negative charge in the 1-position of the purine (3-pyrimidine) base of the nucleotide for mutual transitions between the Na- and K-conformations of Na,K-ATPase they used two analogs of ATP: N 1 -hydroxy-ATP, possessing proton acceptor capacity, and N 1 -methoxy-ATP, in the molecule of which the negative charge is quenched by a methyl group. The first substrate supports active accumulation of Na + in proteoliposomes at the same rate as ATP, whereas the second substrate is relatively ineffective

  19. Investigation on U - O - Na, Pu - O - Na and U,Pu - O - Na phase diagrams

    International Nuclear Information System (INIS)

    Pillon, S.

    1989-03-01

    The thermochemical interaction between the nuclear fuel (uranium and plutonium mixed oxides) and the sodium has been investigated and particularly the three phase diagrams: U - O - Na; Pu - O - Na; U,Pu - O - Na. High temperature neutron diffraction, microcalorimetry and powder X-ray diffraction were used for the characterization of the compounds synthetized. This study allowed to complete the knowledge about each of these diagrams and to measure some physical and thermal properties on the compounds. The limits on the modelization of the fuel-sodium interaction are discussed from the results of the UO 2 - Na reaction [fr

  20. Measurement of exchangeable sodium: 22Na or 24Na

    International Nuclear Information System (INIS)

    Smith, T.; Edmonds, C.J.

    1987-01-01

    A case is made for the use of 22 Na in low activities in preference to 24 Na for routine diagnostic estimation of exchangeable sodium, and is based chiefly on considerations of availability, cost and radiation dosimetry. A method in which only 37 kBq (1 μCi) 22 Na is administered orally is shown to be sufficiently accurate and to possess distinct advantages in terms of cost and convenience with a committed radiation dose no greater than that for a measurement using 24 Na. (author)

  1. Suppression of Na interstitials in Na-F codoped ZnO

    Science.gov (United States)

    Huo, Wenxing; Mei, Zengxia; Tang, Aihua; Liang, Huili; Du, Xiaolong

    2018-04-01

    Controlling the formation of interstitial Na (Nai) self-compensating defects has been a long-term physics problem for effective Na doping in ZnO. Herein, we present an experimental approach to the suppression of Nai defects in ZnO via Na and F codoping under an oxygen-rich condition during the molecular beam epitaxy growth process. It is found that the incorporation of such large numbers of Na and F dopants (˜1020 cm-3) does not cause an obvious influence on the lattice parameters. Hall-effect measurements demonstrate that F doping efficiently raises the Fermi level (EF) of ZnO films, which is expected to make the formation energy of Nai and NaZn increase and decrease, respectively. Most of the Na atoms occupy the substitutional Zn sites, and the formation of Nai is suppressed consequently. Secondary ion mass spectrometry measurements reveal that F and Na atoms are tightly bonded together due to their strong Coulomb interaction. The enhanced deep level emission (DLE) in ZnO:Na-F is ascribed to the considerable amount of isolated Zn vacancy (VZn) defects induced by the elevated EF and the formation of neutral (" separators="| FO + - Na Zn - ) 0 complexes. On the other hand, formation of (" separators="| FO + - VZn 2 - ) - complexes in ZnO:F exhausts most of the isolated Zn vacancies, leading to the disappearance of the DLE band.

  2. OGLAŠEVANJE NA DRUŽBENIH OMREŽJIH NA PRIMERU FACEBOOKA

    OpenAIRE

    Novak, Martina

    2012-01-01

    V diplomskem delu obravnavamo družbene medije kot novo priložnost za promocijo in oglaševanje podjetij. Spoznali smo družbena omrežja na splošno in nekaj teh, ki jih uporabljamo tudi v Sloveniji na kratko predstavili. Podrobneje smo se osredotočili na družbeno omrežje Facebook, predvsem na samo spletno stran, njen izgled in storitve, ki jih ponuja uporabnikom. V nalogi je podrobneje opisan Facebook kot orodje za uporabo oglaševanja. Spoznali smo brezplačne in plačljive načine promocije in ogl...

  3. Na+,K+-ATPase Na+ affinity in rat skeletal muscle fiber types

    DEFF Research Database (Denmark)

    Kristensen, Michael; Juel, Carsten

    2010-01-01

    Previous studies in expression systems have found different ion activation of the Na(+)/K(+)-ATPase isozymes, which suggest that different muscles have different ion affinities. The rate of ATP hydrolysis was used to quantify Na(+),K(+)-ATPase activity, and the Na(+) affinity of Na(+),K(+)-ATPase...

  4. Crystal structure of Na+, K(+)-ATPase in the Na(+)-bound state.

    Science.gov (United States)

    Nyblom, Maria; Poulsen, Hanne; Gourdon, Pontus; Reinhard, Linda; Andersson, Magnus; Lindahl, Erik; Fedosova, Natalya; Nissen, Poul

    2013-10-04

    The Na(+), K(+)-adenosine triphosphatase (ATPase) maintains the electrochemical gradients of Na(+) and K(+) across the plasma membrane--a prerequisite for electrical excitability and secondary transport. Hitherto, structural information has been limited to K(+)-bound or ouabain-blocked forms. We present the crystal structure of a Na(+)-bound Na(+), K(+)-ATPase as determined at 4.3 Å resolution. Compared with the K(+)-bound form, large conformational changes are observed in the α subunit whereas the β and γ subunit structures are maintained. The locations of the three Na(+) sites are indicated with the unique site III at the recently suggested IIIb, as further supported by electrophysiological studies on leak currents. Extracellular release of the third Na(+) from IIIb through IIIa, followed by exchange of Na(+) for K(+) at sites I and II, is suggested.

  5. 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

  6. Meltability in system of K2TaF7-NaF-NaCl-KCl

    International Nuclear Information System (INIS)

    Kartsev, V.E.; Kovalev, F.V.; Korshunov, B.G.

    1975-01-01

    Thermographic and visual-polythermal techniques were used to study the meltability in K 2 TaF 7 -NaF-NaCl-KCl system. The tetrahedron-forming sections NaF-NaCl-K 2 TaF 7 xKCl and NaF-K 2 TaF 7 xKCl-2K 2 TaF 7 xNaCl divide the concentration tetrahedron into three particular tetrahedra: NaF-K 2 TaF 7 xKCl-2K 2 TaF 7 xNaCl-K 2 TaF 7 , NaF-NaCl-K 2 TaF 7 xKCl-2K 2 TaF 7 xaCl, and NaF-NaCl-KCl-K 2 TaF 7 xKCl. Non-variant equilibrium points in all of the particular four-component systems have been determined

  7. Active transport of Na/sup +/ by reconstituted Na,K-ATPase

    Energy Technology Data Exchange (ETDEWEB)

    Boldyrev, A.A.; Svinukhova, I.A.

    1987-02-20

    The ability of ATP, CTP, ITP, GTP, and UTP to support ouabain-sensitive accumulation of Na/sup +/ by proteoliposomes with a reconstituted Na/K-pump was investigated. At a low (Na/sup +/)/(K/sup +/) ratio in the medium (20 mM/50 mM), a correlation is observed between the proton-accepting capacity of the nucleotide and its effectiveness as a substrate of active transport. To test the hypothesis of the importance of the presence of a negative charge in the 1-position of the purine (3-pyrimidine) base of the nucleotide for mutual transitions between the Na- and K-conformations of Na,K-ATPase they used two analogs of ATP: N/sub 1/-hydroxy-ATP, possessing proton acceptor capacity, and N/sub 1/-methoxy-ATP, in the molecule of which the negative charge is quenched by a methyl group. The first substrate supports active accumulation of Na/sup +/ in proteoliposomes at the same rate as ATP, whereas the second substrate is relatively ineffective.

  8. Relationship between intracellular Na+ concentration and reduced Na+ affinity in Na+,K+-ATPase mutants causing neurological disease

    DEFF Research Database (Denmark)

    Toustrup-Jensen, Mads Schak; Einholm, Anja P.; Schack, Vivien

    The neurological disorders familial hemiplegic migraine type 2 (FHM2), alternating hemiplegia of childhood (AHC), and rapid-onset dystonia parkinsonism (RDP) are caused by mutations of Na+,K+-ATPase α2 and α3 isoforms, expressed in glial and neuronal cells, respectively. Although these disorders......, addressing the question to what extent they cause a change of the intracellular Na+ and K+ concentrations ([Na+]i and [K+]i) in COS cells. C-terminal extension mutants generally showed dramatically reduced Na+ affinity without disturbance of K+ binding, as did other RDP mutants. No phosphorylation from ATP...

  9. 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.

  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. MOŽNOSTI VSTOPA NA TUJE TRGE NA PRIMERU PODJETJA AWOODTURE

    OpenAIRE

    Orličnik, Urša

    2014-01-01

    Danes pojavljanje podjetja samo na domačem trgu ni več dovolj. Spremembe okolja, naraščanje konkurence ter hiter tehnološki napredek, silijo podjetja k nenehnemu prilagajanju in iskanju novih priložnosti tako na domačem kot tudi na tujem trgu. Internacionalizacija podjetja tako postaja vedno bolj pomemembna za preživetje podjetja. Internacionalizacija se v najširšem smislu nanaša na vse oblike mednarodnega ekonomskega sodelovanja. Je dinamičen proces, kateremu nujno sledi sprememba stanja...

  12. Na/K pump inactivation, subsarcolemmal Na measurements, and cytoplasmic ion turnover kinetics contradict restricted Na spaces in murine cardiac myocytes

    OpenAIRE

    Lu, Fang-Min; Hilgemann, Donald W.

    2017-01-01

    The Na/K pump exports cytoplasmic Na ions while importing K ions, and its activity is thought to be affected by restricted intracellular Na diffusion in cardiac myocytes. Lu and Hilgemann find instead that the pump can enter an inactivated state and that inactivation can be relieved by cytoplasmic Na.

  13. Vpliv toplotnih mostov na porabo energije za ogrevanje na primeru osnovne šole

    OpenAIRE

    Megušar, Primož

    2015-01-01

    Na primeru Osnovne šole Dobrova sem preveril, kakšen vpliv imajo dejanski toplotni mostovi na porabo energije za ogrevanje. Iz načrtov stavbe sem evidentiral vse toplotne mostove, kateri vplivajo na porabo energije. Tem toplotnim mostovom sem nato v standardu SIST EN ISO 14683 poiskal ustrezne približke. Nato sem s programom TOST izvedel tri simulacije. V prvem primeru toplotnih mostov nisem upošteval. V drugem primeru sem toplotne mostove upošteval na poenostavljen način, v zadnjem primeru p...

  14. Na and K dependence of the Na/K pump in cystic fibrosis fibroblasts.

    OpenAIRE

    Reznik, V M; Schneider, J A; Mendoza, S A

    1981-01-01

    The Na and K dependence of the Na/K pump was measured in skin fibroblasts from patients with cystic fibrosis and age/sex-matched controls. Under basal conditions, there was no difference between control and cystic fibrosis cells in protein per cell, intracellular Na and K content, or Na/K pump activity (measured as ouabain-sensitive 86Rb uptake). There was no difference in the Na dependence of the Na/K pump between cystic fibrosis cells and control cells. In cells from patients with cystic fi...

  15. Vliv mikroflóry na senzorické vlastnosti vína

    OpenAIRE

    Petrášová, Ludmila

    2014-01-01

    Tato bakalářská práce se zabývá vlivem mikroflóry na senzorické vlastnosti vína. Teoretická část informuje o botanickém popisu hroznů vína Veltlínské zelené, dále o jeho složení, o technologii zpracování bílého vína a o vlivu kvasinek na aromatický profil vína. V další části popisuje metodu stanovení aromaticky aktivních látek pomocí plynové chromatografie v kombinaci s mikroextrakcí tuhou fází (SPME-GC). Cílem experimentální části bylo proměřit vzorky 4 různých moštů odrůdy Veltlínské zelené...

  16. 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

  17. 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.

  18. 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.

  19. 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)

  20. Study of the Na-C-O and Na-H-O ternary systems in the sodium rich corner

    International Nuclear Information System (INIS)

    Maupre, J.-P.

    1978-02-01

    The purpose of this study is to provide a contribution to the understanding of the sodium - carbon - oxygen and sodium - hydrogen - oxygen ternary systems in the sodium rich corner. In order to do this the Na-NaH-Na 2 O-NaOH phase diagram was completed and the Na-Na 2 O-Na 2 CO 3 -C phase diagram was outlined. This work is made up of two parts. The first is devoted to a critical literature survey essential to establish correct phase diagrams. The second is an experimental study followed by a discussion collating our finding to the literary data. The basic experimental technique used is differential thermal analysis (DTA) but it has been completed by quenching, X-ray and chemical analysis methods. The proposed phase diagrams imply that Na-NaH-Na 2 O-NaOH and Na-Na 2 O-Na 2 CO 3 -C systems are reciprocal ternary systems. Temperatures of stable pairs reversal are respectively 410 and 690 0 C. The stable pairs are Na-NaOH and Na-Na 2 CO 3 at elevated temperature, Na 2 O-NaH and Na 2 O-C at low temperature [fr

  1. 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

  2. Response of saliva Na/K ratio to changing Na supply of lactating cows under tropical conditions.

    Science.gov (United States)

    Thiangtum, Wandee; Schonewille, J Thomas; Verstegen, Martin Wa; Arsawakulsudhi, Supot; Rukkwamsuk, Theera; Hendriks, Wouter H

    2017-06-01

    Factorial determination of the sodium (Na) requirement of heat-stressed lactating cows is hindered by accurate estimates of the Na losses through sweat. Direct studies, therefore, may be needed requiring information on the time course of healthy animals to become Na depleted and the subsequent rate of repletion. The rate of Na depletion and subsequent rate of Na repletion with two levels of dietary Na to lactating dairy cows housed under tropical conditions were investigated using the salivary Na/K. The 12 lactating cows (salivary Na/K ratio 14.6) rapidly developed clinical signs of Na deficiency, including pica, polyuria and polydipsia, reduced body weight and reduced milk yield when fed a low-Na ration (0.33 g kg -1 dry matter (DM)) for 3 weeks. Deficiency symptoms were associated with a rapid decrease in salivary Na/K ratio to cows with NaCl to a ration concentration of 1.1 or 1.6 g Na kg -1 DM for 5 weeks did not restore salivary Na/K ratio to values of >6. A daily Na intake of heat-stressed lactating cows to a ration intake of 1.6 g Na kg -1 DM was insufficient to restore Na deficiency. One week was sufficient to deplete heat-stressed lactating cows of Na, allowing for rapid dose-response studies utilizing the salivary Na/K ratio as a parameter for Na status of cows under tropical conditions. © 2016 Society of Chemical Industry. © 2016 Society of Chemical Industry.

  3. Glutathionylation-Dependence of Na+-K+-Pump Currents Can Mimic Reduced Subsarcolemmal Na+ Diffusion

    Science.gov (United States)

    Garcia, Alvaro; Liu, Chia-Chi; Cornelius, Flemming; Clarke, Ronald J.; Rasmussen, Helge H.

    2016-01-01

    The existence of a subsarcolemmal space with restricted diffusion for Na+ in cardiac myocytes has been inferred from a transient peak electrogenic Na+-K+ pump current beyond steady state on reexposure of myocytes to K+ after a period of exposure to K+-free extracellular solution. The transient peak current is attributed to enhanced electrogenic pumping of Na+ that accumulated in the diffusion-restricted space during pump inhibition in K+-free extracellular solution. However, there are no known physical barriers that account for such restricted Na+ diffusion, and we examined if changes of activity of the Na+-K+ pump itself cause the transient peak current. Reexposure to K+ reproduced a transient current beyond steady state in voltage-clamped ventricular myocytes as reported by others. Persistence of it when the Na+ concentration in patch pipette solutions perfusing the intracellular compartment was high and elimination of it with K+-free pipette solution could not be reconciled with restricted subsarcolemmal Na+ diffusion. The pattern of the transient current early after pump activation was dependent on transmembrane Na+- and K+ concentration gradients suggesting the currents were related to the conformational poise imposed on the pump. We examined if the currents might be accounted for by changes in glutathionylation of the β1 Na+-K+ pump subunit, a reversible oxidative modification that inhibits the pump. Susceptibility of the β1 subunit to glutathionylation depends on the conformational poise of the Na+-K+ pump, and glutathionylation with the pump stabilized in conformations equivalent to those expected to be imposed on voltage-clamped myocytes supported this hypothesis. So did elimination of the transient K+-induced peak Na+-K+ pump current when we included glutaredoxin 1 in patch pipette solutions to reverse glutathionylation. We conclude that transient K+-induced peak Na+-K+ pump current reflects the effect of conformation-dependent β1 pump subunit

  4. Glutathionylation-Dependence of Na(+)-K(+)-Pump Currents Can Mimic Reduced Subsarcolemmal Na(+) Diffusion.

    Science.gov (United States)

    Garcia, Alvaro; Liu, Chia-Chi; Cornelius, Flemming; Clarke, Ronald J; Rasmussen, Helge H

    2016-03-08

    The existence of a subsarcolemmal space with restricted diffusion for Na(+) in cardiac myocytes has been inferred from a transient peak electrogenic Na(+)-K(+) pump current beyond steady state on reexposure of myocytes to K(+) after a period of exposure to K(+)-free extracellular solution. The transient peak current is attributed to enhanced electrogenic pumping of Na(+) that accumulated in the diffusion-restricted space during pump inhibition in K(+)-free extracellular solution. However, there are no known physical barriers that account for such restricted Na(+) diffusion, and we examined if changes of activity of the Na(+)-K(+) pump itself cause the transient peak current. Reexposure to K(+) reproduced a transient current beyond steady state in voltage-clamped ventricular myocytes as reported by others. Persistence of it when the Na(+) concentration in patch pipette solutions perfusing the intracellular compartment was high and elimination of it with K(+)-free pipette solution could not be reconciled with restricted subsarcolemmal Na(+) diffusion. The pattern of the transient current early after pump activation was dependent on transmembrane Na(+)- and K(+) concentration gradients suggesting the currents were related to the conformational poise imposed on the pump. We examined if the currents might be accounted for by changes in glutathionylation of the β1 Na(+)-K(+) pump subunit, a reversible oxidative modification that inhibits the pump. Susceptibility of the β1 subunit to glutathionylation depends on the conformational poise of the Na(+)-K(+) pump, and glutathionylation with the pump stabilized in conformations equivalent to those expected to be imposed on voltage-clamped myocytes supported this hypothesis. So did elimination of the transient K(+)-induced peak Na(+)-K(+) pump current when we included glutaredoxin 1 in patch pipette solutions to reverse glutathionylation. We conclude that transient K(+)-induced peak Na(+)-K(+) pump current reflects the effect

  5. Crystal structure of a Na+-bound Na+,K+-ATPase preceding the E1P state.

    Science.gov (United States)

    Kanai, Ryuta; Ogawa, Haruo; Vilsen, Bente; Cornelius, Flemming; Toyoshima, Chikashi

    2013-10-10

    Na(+),K(+)-ATPase pumps three Na(+) ions out of cells in exchange for two K(+) taken up from the extracellular medium per ATP molecule hydrolysed, thereby establishing Na(+) and K(+) gradients across the membrane in all animal cells. These ion gradients are used in many fundamental processes, notably excitation of nerve cells. Here we describe 2.8 Å-resolution crystal structures of this ATPase from pig kidney with bound Na(+), ADP and aluminium fluoride, a stable phosphate analogue, with and without oligomycin that promotes Na(+) occlusion. These crystal structures represent a transition state preceding the phosphorylated intermediate (E1P) in which three Na(+) ions are occluded. Details of the Na(+)-binding sites show how this ATPase functions as a Na(+)-specific pump, rejecting K(+) and Ca(2+), even though its affinity for Na(+) is low (millimolar dissociation constant). A mechanism for sequential, cooperative Na(+) binding can now be formulated in atomic detail.

  6. Na+-H+ exchange and Na+-dependent transport systems in streptozotocin diabetic rat kidneys

    International Nuclear Information System (INIS)

    El-Seifi, S.; Freiberg, J.M.; Kinsella, F.J.; Cheng, L.; Sacktor, B.

    1987-01-01

    The streptozotocin-induced diabetic rat was used to test the hypothesis that Na + -H + exchange activity in the proximal tubule luminal membrane would be increased in association with renal hypertrophy, altered glomerular hemodynamics, enhanced filtered load and tubular reabsorption of 22 Na + , and stimulated 22 Na= pump activity in the basolateral membrane, previously reported characteristics of this experimental animal model. Amiloride-sensitive H + gradient-dependent Na + uptake and Na + gradient-dependent H + flux were increased in brush-border membrane vesicles from the streptozotocin-treated animals. Na + gradient-dependent uptakes of phosphate, D-glucose, L-proline, and myoinositol were decreased in the drug-induced diabetic animals. These membrane transport alterations were not found when the streptozotocin-diabetic animals were treated with insulin

  7. The two C-terminal tyrosines stabilize occluded Na/K pump conformations containing Na or K ions.

    Science.gov (United States)

    Vedovato, Natascia; Gadsby, David C

    2010-07-01

    Interactions of the three transported Na ions with the Na/K pump remain incompletely understood. Na/K pump crystal structures show that the extended C terminus of the Na,K-adenosine triphosphatase (ATPase) alpha subunit directly contacts transmembrane helices. Deletion of the last five residues (KETYY in almost all Na/K pumps) markedly lowered the apparent affinity for Na activation of pump phosphorylation from ATP, a reflection of cytoplasmic Na affinity for forming the occluded E1P(Na3) conformation. ATPase assays further suggested that C-terminal truncations also interfere with low affinity Na interactions, which are attributable to extracellular effects. Because extracellular Na ions traverse part of the membrane's electric field to reach their binding sites in the Na/K pump, their movements generate currents that can be monitored with high resolution. We report here electrical measurements to examine how Na/K pump interactions with extracellular Na ions are influenced by C-terminal truncations. We deleted the last two (YY) or five (KESYY) residues in Xenopus laevis alpha1 Na/K pumps made ouabain resistant by either of two kinds of point mutations and measured their currents as 10-mM ouabain-sensitive currents in Xenopus oocytes after silencing endogenous Xenopus Na/K pumps with 1 microM ouabain. We found the low affinity inhibitory influence of extracellular Na on outward Na/K pump current at negative voltages to be impaired in all of the C-terminally truncated pumps. Correspondingly, voltage jump-induced transient charge movements that reflect pump interactions with extracellular Na ions were strongly shifted to more negative potentials; this signals a several-fold reduction of the apparent affinity for extracellular Na in the truncated pumps. Parallel lowering of Na affinity on both sides of the membrane argues that the C-terminal contacts provide important stabilization of the occluded E1P(Na3) conformation, regardless of the route of Na ion entry into the

  8. Anion-coupled Na efflux mediated by the human red blood cell Na/K pump

    International Nuclear Information System (INIS)

    Dissing, S.; Hoffman, J.F.

    1990-01-01

    The red cell Na/K pump is known to continue to extrude Na when both Na and K are removed from the external medium. Because this ouabain-sensitive flux occurs in the absence of an exchangeable cation, it is referred to as uncoupled Na efflux. This flux is also known to be inhibited by 5 mM Nao but to a lesser extent than that inhibitable by ouabain. Uncoupled Na efflux via the Na/K pump therefore can be divided into a Nao-sensitive and Nao-insensitive component. We used DIDS-treated, SO4-equilibrated human red blood cells suspended in HEPES-buffered (pHo 7.4) MgSO4 or (Tris)2SO4, in which we measured 22Na efflux, 35SO4 efflux, and changes in the membrane potential with the fluorescent dye, diS-C3 (5). A principal finding is that uncoupled Na efflux occurs electroneurally, in contrast to the pump's normal electrogenic operation when exchanging Nai for Ko. This electroneutral uncoupled efflux of Na was found to be balanced by an efflux of cellular anions. (We were unable to detect any ouabain-sensitive uptake of protons, measured in an unbuffered medium at pH 7.4 with a Radiometer pH-STAT.) The Nao-sensitive efflux of Nai was found to be 1.95 +/- 0.10 times the Nao-sensitive efflux of (SO4)i, indicating that the stoichiometry of this cotransport is two Na+ per SO4=, accounting for 60-80% of the electroneutral Na efflux. The remainder portion, that is, the ouabain-sensitive Nao-insensitive component, has been identified as PO4-coupled Na transport and is the subject of a separate paper. That uncoupled Na efflux occurs as a cotransport with anions is supported by the result, obtained with resealed ghosts, that when internal and external SO4 was substituted by the impermeant anion, tartrate i,o, the efflux of Na was inhibited 60-80%. This inhibition could be relieved by the inclusion, before DIDS treatment, of 5 mM Cli,o

  9. 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.

  10. Na5NbO5 and Na5TaO5 phases

    International Nuclear Information System (INIS)

    Darriet, J.; Maazaz, A.; Bouloux, J.C.; Delmas, C.

    1982-01-01

    New ternary oxides of formulas Na 5 NbO 5 and Na 5 TaO 5 have been prepared. They crystallize in the monoclinic system (space group C2/c). The crystal structure of Na 5 NbO 5 has been determined. It derives from a NaCl-type structure by ordering of the cations and of the oxygen vacancies in the anionic sublattice, the corresponding formula being Nasub(5/6)Nbsub(1/6)Osub(5/6)vacant sub(1/6). Sodium and niobium have a distorted square-pyramidal surrounding. (author)

  11. Synthesis of Na-A and/or Na-X zeolite/porous carbon composites from carbonized rice husk

    International Nuclear Information System (INIS)

    Katsuki, Hiroaki; Komarneni, Sridhar

    2009-01-01

    Na-A and/or Na-X zeolite/porous carbon composites were prepared under hydrothermal conditions by NaOH dissolution of silica first from carbonized rice husk followed by addition of NaAlO 2 and in situ crystallization of zeolites i.e., using a two-step process. When a one-step process was used, both Na-A and Na-X zeolites crystallized on the surface of carbon. Na-A or Na-X zeolite crystals were prepared on the porous carbonized rice husk at 90 deg. C for 2-6 h by changing the SiO 2 /Al 2 O 3 , H 2 O/Na 2 O and Na 2 O/SiO 2 molar ratios of precursors in the two-step process. The surface area and NH 4 + -cation exchange capacity (CEC) of Na-A zeolite/porous carbon were found to be 171 m 2 /g and 506 meq/100 g, respectively, while those of Na-X zeolite/porous carbon composites were 676 m 2 /g and 317 meq/100 g, respectively. Na-A and Na-X zeolites are well-known microporous and hydrophilic materials while carbonized rice husk was found to be mesoporous (pores of ∼3.9 nm) and hydrophobic. These hybrid microporous-mesoporous and hydrophilic-hydrophobic composites are expected to be useful for decontamination of metal cations as well as organic contaminants simultaneously. - Graphical Abstract: Novel Na-X zeolite/porous carbon composite.

  12. Equilibrium chemical transformations in NaPO3 + NaCl melts

    International Nuclear Information System (INIS)

    Kovarskaya, E.N.; Rodionov, Yu.I.

    1988-01-01

    Because of the problems of the burial of solidified radioactive wastes into different geological rock formations, in particular into massives of rock-salt, the state of molten polyphosphate-chloride mixtures (taking into account the chemical character of the interaction of their components) for a prolonged period of time. The equilibrium products of the reaction in the NaPO 3 -NaCl system were studied in melts in air in the composition range of 30-70 mole % NaCl. It was shown that with increase in the NaCl content in the mixtures, the polyphosphate gradually depolymerizes to sodium tri-, di-, and monophosphates, and the composition of the equilibrium melts is dependent only on the ratio between the components in the initial molten mixtures. The time until the equilibrium is attained is shorter, the higher is the experimental temperature

  13. Long-Range Effects of Na(+) Binding in Na,K-ATPase Reported by ATP.

    Science.gov (United States)

    Middleton, David A; Fedosova, Natalya U; Esmann, Mikael

    2015-12-01

    This paper addresses the question of long-range interactions between the intramembranous cation binding sites and the cytoplasmic nucleotide binding site of the ubiquitous ion-transporting Na,K-ATPase using (13)C cross-polarization magic-angle spinning (CP-MAS) solid-state nuclear magnetic resonance. High-affinity ATP binding is induced by the presence of Na(+) as well as of Na-like substances such as Tris(+), and these ions are equally efficient promoters of nucleotide binding. CP-MAS analysis of bound ATP with Na,K-ATPase purified from pig kidney membranes reveals subtle differences in the nucleotide interactions within the nucleotide site depending on whether Na(+) or Tris(+) is used to induce binding. Differences in chemical shifts for ATP atoms C1' and C5' observed in the presence of Na(+) or Tris(+) suggest alterations in the residues surrounding the bound nucleotide, hydrogen bonding, and/or conformation of the ribose ring. This is taken as evidence of a long-distance communication between the Na(+)-filled ion sites in the membrane interior and the nucleotide binding site in the cytoplasmic domain and reflects the first conformational change ultimately leading to phosphorylation of the enzyme. Stopped-flow fluorescence measurements with the nucleotide analogue eosin show that the dissociation rate constant for eosin is larger in Tris(+) than in Na(+), giving kinetic evidence of the difference in structural effects of Na(+) and Tris(+). According to the recent crystal structure of the E1·AlF4(-)·ADP·3Na(+) form, the coupling between the ion binding sites and the nucleotide side is mediated by, among others, the M5 helix.

  14. Interaction between Na+/K+-pump and Na+/Ca2+-exchanger modulates intercellular communication.

    Science.gov (United States)

    Matchkov, Vladimir V; Gustafsson, Helena; Rahman, Awahan; Briggs Boedtkjer, Donna M; Gorintin, Sarah; Hansen, Anne Kirstine; Bouzinova, Elena V; Praetorius, Helle A; Aalkjaer, Christian; Nilsson, Holger

    2007-04-13

    Ouabain, a specific inhibitor of the Na(+)/K(+)-pump, has previously been shown to interfere with intercellular communication. Here we test the hypothesis that the communication between vascular smooth muscle cells is regulated through an interaction between the Na(+)/K(+)-pump and the Na(+)/Ca(2+)-exchanger leading to an increase in the intracellular calcium concentration ([Ca(2+)](i)) in discrete areas near the plasma membrane. [Ca(2+)](i) in smooth muscle cells was imaged in cultured rat aortic smooth muscle cell pairs (A7r5) and in rat mesenteric small artery segments simultaneously with force. In A7r5 coupling between cells was estimated by measuring membrane capacitance. Smooth muscle cells were uncoupled when the Na(+)/K(+)-pump was inhibited either by a low concentration of ouabain, which also caused a localized increase of [Ca(2+)](i) near the membrane, or by ATP depletion. Reduction of Na(+)/K(+)-pump activity by removal of extracellular potassium ([K(+)](o)) also uncoupled cells, but only after inhibition of K(ATP) channels. Inhibition of the Na(+)/Ca(2+)-exchange activity by SEA0400 or by a reduction of the equilibrium potential (making it more negative) also uncoupled the cells. Depletion of intracellular Na(+) and clamping of [Ca(2+)](i) at low concentrations prevented the uncoupling. The experiments suggest that the Na(+)/K(+)-pump may affect gap junction conductivity via localized changes in [Ca(2+)](i) through modulation of Na(+)/Ca(2+)-exchanger activity.

  15. Intracellular Na(+) and metabolic modulation of Na/K pump and excitability in the rat suprachiasmatic nucleus neurons.

    Science.gov (United States)

    Wang, Yi-Chi; Yang, Jyh-Jeen; Huang, Rong-Chi

    2012-10-01

    Na/K pump activity and metabolic rate are both higher during the day in the suprachiasmatic nucleus (SCN) that houses the circadian clock. Here we investigated the role of intracellular Na(+) and energy metabolism in regulating Na/K pump activity and neuronal excitability. Removal of extracellular K(+) to block the Na/K pump excited SCN neurons to fire at higher rates and return to normal K(+) to reactivate the pump produced rebound hyperpolarization to inhibit firing. In the presence of tetrodotoxin to block the action potentials, both zero K(+)-induced depolarization and rebound hyperpolarization were blocked by the cardiac glycoside strophanthidin. Ratiometric Na(+) imaging with a Na(+)-sensitive fluorescent dye indicated saturating accumulation of intracellular Na(+) in response to pump blockade with zero K(+). The Na(+) ionophore monensin also induced Na(+) loading and hyperpolarized the membrane potential, with the hyperpolarizing effect of monensin abolished in zero Na(+) or by pump blockade. Conversely, Na(+) depletion with Na(+)-free pipette solution depolarized membrane potential but retained residual Na/K pump activity. Cyanide inhibition of oxidative phosphorylation blocked the Na/K pump to depolarize resting potential and increase spontaneous firing in most cells, and to raise intracellular Na(+) levels in all cells. Nonetheless, the Na/K pump was incompletely blocked by cyanide but completely blocked by iodoacetate to inhibit glycolysis, indicating the involvement of both oxidative phosphorylation and glycolysis in fueling the Na/K pump. Together, the results indicate the importance of intracellular Na(+) and energy metabolism in regulating Na/K pump activity as well as neuronal excitability in the SCN neurons.

  16. Synthesis of zeolites Na-A and Na-X from tablet compressed and calcinated coal fly ash

    Science.gov (United States)

    Hu, Tao; Gao, Wenyan; Liu, Xin; Zhang, Yifu; Meng, Changgong

    2017-10-01

    Zeolites Na-A and Na-X are important synthetic zeolites widely used for separation and adsorption in industry. It is of great significance to develop energy-efficient routines that can synthesize zeolites Na-A and Na-X from low-cost raw materials. Coal fly ash (CFA) is the major residue from the combustion of coal and biomass containing more than 85% SiO2 and Al2O3, which can readily replace the conventionally used sodium silicate and aluminate for zeolite synthesis. We used Na2CO3 to replace the expensive NaOH used for the calcination of CFA and showed that tablet compression can enhance the contact with Na2CO3 for the activation of CFA through calcination for the synthesis of zeolites Na-A and Na-X under mild conditions. We optimized the control variables for zeolite synthesis and showed that phase-pure zeolite Na-A can be synthesized with CFA at reactant molar ratio, hydrothermal reaction temperature and reaction time of 1.3Na2O: 0.6Al2O3: 1SiO2: 38H2O at 80°C for 6 h, respectively, while phase-pure zeolite Na-X can be synthesized at 2.2Na2O: 0.2Al2O3: 1SiO2: 88H2O at 100°C for 8 h, respectively. The composition, morphology, specific surface area, vibration spectrum and thermogravimetry of synthesized Na-A and Na-X were further characterized.

  17. The CERES / NA45 experiment

    CERN Multimedia

    Laurent Guiraud

    2000-01-01

    Ceres is one of the second generation heavy ion experiments at CERN's SPS. It is dedicated to the study of electron-positron pairs in relativistic nuclear collisions. NA45 is one of the seven experiments (NA44, NA45, NA49, NA50, NA52, WA97/NA57 and WA98) involved in CERN's Heavy Ion programme which provided evidence for the existence of a new state of matter, the quark-gluon plasma. In this state, quarks, instead of being bound up into more complex particles such as protons and neutrons, are liberated and roam freely. Theory predicts that this state must have existed at about 10 microseconds after the Big Bang, before the formation of matter as we know it today.

  18. The rapid-onset dystonia parkinsonism mutation D923N of the Na+, K+-ATPase alpha3 isoform disrupts Na+ interaction at the third Na+ site.

    Science.gov (United States)

    Einholm, Anja Pernille; Toustrup-Jensen, Mads S; Holm, Rikke; Andersen, Jens Peter; Vilsen, Bente

    2010-08-20

    Rapid-onset dystonia parkinsonism (RDP), a rare neurological disorder, is caused by mutation of the neuron-specific alpha3-isoform of Na(+), K(+)-ATPase. Here, we present the functional consequences of RDP mutation D923N. Relative to the wild type, the mutant exhibits a remarkable approximately 200-fold reduction of Na(+) affinity for activation of phosphorylation from ATP, reflecting a defective interaction of the E(1) form with intracellular Na(+). This is the largest effect on Na(+) affinity reported so far for any Na(+), K(+)-ATPase mutant. D923N also affects the interaction with extracellular Na(+) normally driving the E(1)P to E(2)P conformational transition backward. However, no impairment of K(+) binding was observed for D923N, leading to the conclusion that Asp(923) is specifically associated with the third Na(+) site that is selective toward Na(+). The crystal structure of the Na(+), K(+)-ATPase in E(2) form shows that Asp(923) is located in the cytoplasmic half of transmembrane helix M8 inside a putative transport channel, which is lined by residues from the transmembrane helices M5, M7, M8, and M10 and capped by the C terminus, recently found involved in recognition of the third Na(+) ion. Structural modeling of the E(1) form of Na(+), K(+)-ATPase based on the Ca(2+)-ATPase crystal structure is consistent with the hypothesis that Asp(923) contributes to a site binding the third Na(+) ion. These results in conjunction with our previous findings with other RDP mutants suggest that a selective defect in the handling of Na(+) may be a general feature of the RDP disorder.

  19. Recikliranje plastenk na kreativen način

    OpenAIRE

    Pavlin, Suzana

    2017-01-01

    Plastenke, poleg ostalih plastičnih izdelkov, v zadnjih letih predstavljajo pravo katastrofo za okolje. Domnevamo, da se le redko kdo vpraša, kaj se zgodi z njo po tem, ko je iz nje zaužil še zadnjo kapljico vode. Plastenka je lahko kot večina ostalih komunalnih odpadkov ponovno uporabljena, reciklirana, sežgana ali odložena na deponijo. V primeru nespoštovanja Zakona o varstvu okolja pa pristane v naravi, pogosto v morju, kjer prav počasi razpada in negativno vpliva na celoten ekosistem. V d...

  20. Plant Defensins NaD1 and NaD2 Induce Different Stress Response Pathways in Fungi

    Directory of Open Access Journals (Sweden)

    Peter M. Dracatos

    2016-09-01

    Full Text Available Nicotiana alata defensins 1 and 2 (NaD1 and NaD2 are plant defensins from the ornamental tobacco that have antifungal activity against a variety of fungal pathogens. Some plant defensins interact with fungal cell wall O-glycosylated proteins. Therefore, we investigated if this was the case for NaD1 and NaD2, by assessing the sensitivity of the three Aspergillus nidulans (An O-mannosyltransferase (pmt knockout (KO mutants (An∆pmtA, An∆pmtB, and An∆pmtC. An∆pmtA was resistant to both defensins, while An∆pmtC was resistant to NaD2 only, suggesting NaD1 and NaD2 are unlikely to have a general interaction with O-linked side chains. Further evidence of this difference in the antifungal mechanism was provided by the dissimilarity of the NaD1 and NaD2 sensitivities of the Fusarium oxysporum f. sp. lycopersici (Fol signalling knockout mutants from the cell wall integrity (CWI and high osmolarity glycerol (HOG mitogen-activated protein kinase (MAPK pathways. HOG pathway mutants were sensitive to both NaD1 and NaD2, while CWI pathway mutants only displayed sensitivity to NaD2.

  1. Glutamate Water Gates in the Ion Binding Pocket of Na(+) Bound Na(+), K(+)-ATPase

    DEFF Research Database (Denmark)

    Han, Minwoo; Kopec, Wojciech; Solov'yov, Ilia A

    2017-01-01

    III is always protonated. Glutamic acid residues in the three binding sites act as water gates, and their deprotonation triggers water entry to the binding sites. From DFT calculations of Na(+) binding energies, we conclude that three protons in the binding site are needed to effectively bind Na......The dynamically changing protonation states of the six acidic amino acid residues in the ion binding pocket of the Na(+), K(+) -ATPase (NKA) during the ion transport cycle are proposed to drive ion binding, release and possibly determine Na(+) or K(+) selectivity. We use molecular dynamics (MD......(+) from water and four are needed to release them in the next step. Protonation of Asp926 in site III will induce Na(+) release, and Glu327, Glu954 and Glu779 are all likely to be protonated in the Na(+) bound occluded conformation. Our data provides key insights into the role of protons in the Na...

  2. 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

  3. NA62 and NA48/2 results on search for Heavy Neutral Leptons

    Directory of Open Access Journals (Sweden)

    Lamanna Gianluca

    2018-01-01

    Full Text Available In this paper we present new results on upper limits for the search of Heavy Neutral Leptons (HNL with data collected by NA48/2 (2003-2004, NA62-RK (2007 and NA62 (2015 CERN experiments. The data collected with different trigger configuration allow to search for both long and short living heavy neutrinos in the mass range below the kaon mass. In addition the status of the search for K+ → π+vv with the NA62 detector will be briefly presented.

  4. Transmural gradients in Na/K pump activity and [Na+]I in canine ventricle.

    Science.gov (United States)

    Gao, J; Wang, W; Cohen, I S; Mathias, R T

    2005-09-01

    There are well-documented differences in ion channel activity and action potential shape between epicardial (EPI), midmyocardial (MID), and endocardial (ENDO) ventricular myocytes. The purpose of this study was to determine if differences exist in Na/K pump activity. The whole cell patch-clamp was used to measure Na/K pump current (I(P)) and inward background Na(+)-current (I(inb)) in cells isolated from canine left ventricle. All currents were normalized to membrane capacitance. I(P) was measured as the current blocked by a saturating concentration of dihydro-ouabain. [Na(+)](i) was measured using SBFI-AM. I(P)(ENDO) (0.34 +/- 0.04 pA/pF, n = 17) was smaller than I(P)(EPI) (0.68 +/- 0.09 pA/pF, n = 38); the ratio was 0.50 with I(P)(MID) being intermediate (0.53 +/- 0.13 pA/pF, n = 19). The dependence of I(P) on [Na(+)](i) or voltage was essentially identical in EPI and ENDO (half-maximal activation at 9-10 mM [Na(+)](i) or approximately -90 mV). Increasing [K(+)](o) from 5.4 to 15 mM caused both I(P)(ENDO) and I(P)(EPI) to increase, but the ratio remained approximately 0.5. I(inb) in EPI and ENDO were nearly identical ( approximately 0.6 pA/pF). Physiological [Na(+)](i) was lower in EPI (7 +/- 2 mM, n = 31) than ENDO (12 +/- 3 mM, n = 29), with MID being intermediate (9 +/- 3 mM, n = 22). When cells were paced at 2 Hz, [Na(+)](i) increased but the differences persisted (ENDO 14 +/- 3 mM, n = 10; EPI 9 +/- 2 mM, n = 10; and MID intermediate, 11 +/- 2 mM, n = 9). Based on these results, the larger I(P) in EPI appears to reflect a higher maximum turnover rate, which implies either a larger number of active pumps or a higher turnover rate per pump protein. The transmural gradient in [Na(+)](i) means physiological I(P) is approximately uniform across the ventricular wall, whereas transporters that utilize the transmembrane electrochemical gradient for Na(+), such as Na/Ca exchange, have a larger driving force in EPI than ENDO.

  5. Reactions of metal oxides with molten NaPO3 + NaCl mixtures

    International Nuclear Information System (INIS)

    Kovarskaya, E.N.; Mityakhina, V.S.; Rodionov, Yu.I.; Silin, M.Yu.

    1988-01-01

    We consider the dissolution mechanism for iron (III), europium(III), and tin(IV) oxides in molten NaPO 3 + NaCl that are responsible for the peak solubilities. We chose Fe 2 O 3 as the basic material since this occurs in large amounts around damaged metal structures in rock salt mines in a proposed zone for storing vitrified radioactive wastes. Solubility measurement and paper chromatography show that Fe 2 O 3 dissolves in molten NaPO 3 + NaCl in air by reaction with the solvent to give double iron and sodium diphosphates and monophosphates in accordance with the initial solution-in-the-melt composition, the degree of equilibration, and the temperature. The elevated solubilities for initial NaCl contents close to 30 mole % are due to sodium triphosphates and tricyclophosphates present in these melts. Moessbauer spectroscopy confirms that double iron, europium and tin diphosphates and monophosphates containing sodium occur in these chloride-polyphosphate melts

  6. Na(+),K (+)-ATPase as a docking station: protein-protein complexes of the Na(+),K (+)-ATPase.

    Science.gov (United States)

    Reinhard, Linda; Tidow, Henning; Clausen, Michael J; Nissen, Poul

    2013-01-01

    The Na(+),K(+)-ATPase, or sodium pump, is well known for its role in ion transport across the plasma membrane of animal cells. It carries out the transport of Na(+) ions out of the cell and of K(+) ions into the cell and thus maintains electrolyte and fluid balance. In addition to the fundamental ion-pumping function of the Na(+),K(+)-ATPase, recent work has suggested additional roles for Na(+),K(+)-ATPase in signal transduction and biomembrane structure. Several signaling pathways have been found to involve Na(+),K(+)-ATPase, which serves as a docking station for a fast-growing number of protein interaction partners. In this review, we focus on Na(+),K(+)-ATPase as a signal transducer, but also briefly discuss other Na(+),K(+)-ATPase protein-protein interactions, providing a comprehensive overview of the diverse signaling functions ascribed to this well-known enzyme.

  7. Characterization of Na+-linked and Na+-independent Cl-/HCO3- exchange systems in Chinese hamster lung fibroblasts

    International Nuclear Information System (INIS)

    Cassel, D.; Scharf, O.; Rotman, M.; Cragoe, E.J. Jr.; Katz, M.

    1988-01-01

    The PS120 variant of Chinese hamster lung fibroblasts which lacks Na + /H + exchange activity was used to investigate bicarbonate transport systems and their role in intracellular pH (pH/sub i/) regulation. When pH/sub i/ was decreased by acid load, bicarbonate caused pH/sub i/ increase and stimulated 36 Cl - efflux from the cells, both in a Na + -dependent manner. These results together with previous findings that bicarbonate stimulates 22 Na + uptake in PS120 cells demonstrate the presence of a Na + -linked Cl - /HCO 3 - exchange system. In cells with normal initial pH/sub i/, bicarbonate caused Na + -independent pH/sub i/ increase in Cl - -free solutions and stimulated Na + -independent 36 Cl - efflux, indicating that a Na + -independent Cl - /HCO 3 - exchanger is also present in the cell. Na + -linked and Na + -independent Cl - /HCO 3- exchange is apparently mediated by two distinct systems, since a [(tetrahydrofluorene-7-yl)oxy]acetic acid derivative selectively inhibits the Na + -independent exchanger. An additional distinctive features is a 10-fold lower affinity for chloride of the Na + -linked exchanger. The Na + -linked and Na + -independent Cl - /HCO 3 - exchange systems are likely to protect the cell from acid and alkaline load, respectively

  8. Na/K Pump and Beyond: Na/K-ATPase as a Modulator of Apoptosis and Autophagy

    Directory of Open Access Journals (Sweden)

    Cassiano Felippe Gonçalves-de-Albuquerque

    2017-04-01

    Full Text Available Lung cancer is a leading cause of global cancer deaths. Na/K-ATPase has been studied as a target for cancer treatment. Cardiotonic steroids (CS trigger intracellular signalling upon binding to Na/K-ATPase. Normal lung and tumour cells frequently express different pump isoforms. Thus, Na/K-ATPase is a powerful target for lung cancer treatment. Drugs targeting Na/K-ATPase may induce apoptosis and autophagy in transformed cells. We argue that Na/K-ATPase has a role as a potential target in chemotherapy in lung cancer treatment. We discuss the effects of Na/K-ATPase ligands and molecular pathways inducing deleterious effects on lung cancer cells, especially those leading to apoptosis and autophagy.

  9. Na/K Pump and Beyond: Na/K-ATPase as a Modulator of Apoptosis and Autophagy.

    Science.gov (United States)

    Felippe Gonçalves-de-Albuquerque, Cassiano; Ribeiro Silva, Adriana; Ignácio da Silva, Camila; Caire Castro-Faria-Neto, Hugo; Burth, Patrícia

    2017-04-21

    Lung cancer is a leading cause of global cancer deaths. Na/K-ATPase has been studied as a target for cancer treatment. Cardiotonic steroids (CS) trigger intracellular signalling upon binding to Na/K-ATPase. Normal lung and tumour cells frequently express different pump isoforms. Thus, Na/K-ATPase is a powerful target for lung cancer treatment. Drugs targeting Na/K-ATPase may induce apoptosis and autophagy in transformed cells. We argue that Na/K-ATPase has a role as a potential target in chemotherapy in lung cancer treatment. We discuss the effects of Na/K-ATPase ligands and molecular pathways inducing deleterious effects on lung cancer cells, especially those leading to apoptosis and autophagy.

  10. Subnitride chemistry: A first-principles study of the NaBa3N, Na5Ba3N, and Na16Ba6N phases

    International Nuclear Information System (INIS)

    Oliva, Josep M.

    2005-01-01

    An ab initio study on the electronic structure of the subnitrides NaBa 3 N, Na 5 Ba 3 N, and Na 16 Ba 6 N is performed for the first time. The NaBa 3 N and Na 5 Ba 3 N phases consist of infinite 1 ∞ [NBa 6/2 ] strands composed of face-sharing NBa 6 octahedra surrounded by a 'sea' of sodium atoms. The Na 16 Ba 6 N phase consist of discrete [NBa 6 ] octahedra arranged in a body-cubic fashion, surrounded by a 'sea' of sodium atoms. Our calculations suggest that the title subnitrides are metals. Analysis of the electronic structure shows partial interaction of N(2s) with Ba(5p) electrons in the lower energy region for NaBa 3 N and Na 5 Ba 3 N. However, no dispersion is observed for the N(2s) and Ba(5p) bands in the cubic phase Na 16 Ba 6 N. The metallic band below the Fermi level shows a strong mixing of N(2p), Ba(6s), Ba(5d), Ba(6p), Na(3s) and Na(3p) orbitals. The metallic character in these nitrides stems from delocalized electrons corresponding to hybridized 5d l 6s m 6p n barium orbitals which interact with hybridized 3s n 3p m sodium orbitals. Analysis of the electron density and electronic structure in these nitrides shows two different regions: a metallic matrix corresponding to the sodium atoms and the regions around them and heteropolar bonding between nitrogen and barium within the infinite 1 ∞ [NBa 6/2 ] strands of the NaBa 3 N and Na 5 Ba 3 N phases, and within the isolated [NBa 6 ] octahedra of the Na 16 Ba 6 N phase. The nitrogen atoms inside the strands and octahedra are negatively charged, the anionic character of nitrogens being larger in the isolated octahedra of the cubic phase Na 16 Ba 6 N, due to the lack of electron delocalization along one direction as opposed to the other phases. The sodium and barium atoms appear to be slightly negatively and positively charged, the latter to a larger extent. From the computed Ba-N overlap populations as well as the analysis of the contour maps of differences between total density and superposition of

  11. WPŁYW WIEKU NA WYTRZYMAŁOŚĆ NA ŚCISKANIE BETONU MODYFIKOWANEGO DODATKIEM METAKAOLINITU

    Directory of Open Access Journals (Sweden)

    Janusz KONKOL

    Full Text Available W artykule przedstawiono wyniki badań wytrzymałości na ściskanie betonów modyfikowanych dodatkiem metakaolinitu po 2, 3, 7, 14, 28 i 56 dniach dojrzewania. Dodatek metakaolinitu użyto jako częściowy substytut cementu, dokonując wymiany 10% masy cementu na metakaolinit. Udział ten uznawany jest za optymalny z uwagi na inne niż wytrzymałość na ściskanie właściwości betonu, w tym trwałość betonu modyfikowanego metakaolinitem. Badania przeprowadzono także dla betonu tła, betonu bez dodatku metakaolinitu. Betony wykonano przy założeniu stałego stosunku woda/spoiwo, względnie woda/cement wynoszącego 0,45 oraz przy użyciu cementu portlandzkiego CEM I 32,5R, piasku kwarcowego frakcji do 2 mm oraz grysu bazaltowego frakcji do 16 mm. W celu uzyskania pożądanej konsystencji mieszanki betonowej zastosowano upłynniacz na bazie estrów polikarboksylowych. Uzyskane rezultaty badań potwierdziły wysoką aktywność pucolanową metakaolinitu już we wczesnym okresie dojrzewania betonu. W okresie między 3 a 7 dniem dojrzewania stwierdzono wolniejszy przyrost wytrzymałości na ściskanie w betonie niemodyfikowanym metakaolinitem, podczas gdy w betonie, w którym 10% masy cementu zastąpiono metakaolinitem uwidocznił się znaczący przyrost wytrzymałości na ściskanie. Po 2 dniach dojrzewania wytrzymałość na ściskanie betonu tła była nieznacznie wyższa od wytrzymałości na ściskanie betonu modyfikowanego. Korzystny wpływ dodatku metakaolinitu wynikający z jego wysokiej aktywności pucolanowej, jak również z uszczelniającego charakteru tego dodatku obserwowano jest zwłaszcza w okresie między 3 a 14 dniem dojrzewania. W tym okresie obserwowano znaczny przyrost wytrzymałości na ściskanie betonu modyfikowanego w porównaniu z wytrzymałością na ściskanie betonu tła. Po 7 i 14 dniach dojrzewania stwierdzono odpowiednio prawie 25% i 21% wzrost wytrzymałości na ściskanie na skutek użycia metakaolinitu.

  12. Teratological studies of DTPA-CaNa3, DTPA-ZnNa3 and quinamic acid in mice

    International Nuclear Information System (INIS)

    Luo Meichu; Ruan Tianming; Tong Shungao

    1989-01-01

    DTPA-CaNa 3 , DTPA-ZnNa 3 and quinamic acid are effective chelating agents for removing actinide elements from the body. In this experiment, different doses of DTPA-CaNa 3 , DTPA-ZnNa 3 and quinamic acid were given to mice on gestation days 6-10. Eight groups of mice received 0.8 and 2.0 mM/kg of DTPA-CaNa 3 , 3.8, 7.6, and 11.4 mM/kg of DTPA-ZnNa 3 and 0.42, 2.1, and 4.2 mM/kg of quinamic acid. Hypetonic saline and isotonic saline were given to two control groups. DTPA-CaNa 3 and quinamidic acid were found to be much more toxic to fetus of mice than DTPA-ZnNa 3 . When the doses of DTPA-CaMa 3 and quinamidic acid were 20 times higher than the human dose, the number of resorbed fetus was increased and the number and weight of live fetus were reduced. The result of injection with 7.6 mM/kg (200 times of human dose)DTPA-ZnNa 3 and that of injection with isotonic saline are the same. Therefore, we suggest that the DTPA-CaNa 3 and quinamidic acid should not be given to pregnant woman, if chelation therapy is needed, while the much safer DTPA-ZnNa 3 could be used

  13. Na-ion dynamics in Quasi-1D compound NaV2O4

    International Nuclear Information System (INIS)

    Månsson, M; Umegaki, I; Nozaki, H; Higuchi, Y; Sugiyama, J; Kawasaki, I; Watanabe, I; Sakurai, H

    2014-01-01

    We have used the pulsed muon source at ISIS to study high-temperature Na-ion dynamics in the quasi-one-dimensional (Q1D) metallic antiferromagnet NaV 2 O 4 . By performing systematic zero-field and longitudinal-field measurements as a function of temperature we clearly distinguish that the hopping rate increases exponentially above T diff ≈ 250 K. The data is well fitted to an Arrhenius type equation typical for a diffusion process, showing that the Na-ions starts to be mobile above T diff . Such results make this compound very interesting for the tuning of Q1D magnetism using atomic-scale ion-texturing through the periodic potential from ordered Na-vacancies. Further, it also opens the door to possible use of NaV 2 O 4 and related compounds in energy related applications

  14. O Passeio Público do Rio de Janeiro na Literatura, na Pintura e na Fotografia do Século XIX

    Directory of Open Access Journals (Sweden)

    Solange de Aragão

    2012-06-01

    Full Text Available Este artigo tem como objetivo geral e mais amplo chamar a atenção dos pesquisadores para a importância da literatura, da pintura e da fotografia como fontes documentais para a construção da História do Paisagismo no Brasil por meio de um estudo de caso muito particular: o Passeio Público do Rio de Janeiro no século XIX. São objetivos específicos apresentar e analisar o modo como esse espaço livre público aparece na literatura, na pintura e na fotografia desse período, considerando suas transformações paisagísticas.

  15. Solubility of NaNd(CO3)2.6H2O(c) in concentrated Na2CO3 and NaHCO3 solutions

    International Nuclear Information System (INIS)

    Rao, L.; Rai, D.; Felmy, A.R.; Fulton, R.W.; Novak, C.F.

    1996-01-01

    NaNd(CO 3 ) 2 x 6 H 2 O(c) was identified to be the final equilibrium solid phase in suspensions containing concentrated sodium carbonate (0.1 to 2.0 M) and sodium bicarbonate (0.1 to 1.0 M), with either NaNd(CO 3 ) 2 x 6 H 2 O(c) or Nd 2 (CO 3 ) 3 x xH 2 O(s) as initial solids. A thermodynamic model, based on Pitzer's specific into-interaction approach, was developed to interpret the solubility of NaNd(CO 3 ) 2 x 6 H 2 O(c) as functions of sodium carbonate and sodium bicarbonate concentrations. In this model, the solubility data of NaNd(CO 3 ) 2 x 6 H 2 O(c) were explained by assuming the formation of NdCO 3 + , Nd(CO 3 ) 2 - and Nd(CO 3 ) 3 3- species and invoking the specific ion interactions between Na + and Nd(CO 3 ) 3 3- . Ion interaction parameters for Na + -Nd(CO 3 ) 3 3- were developed to fit the solubility data. Based on the model calculations, Nd(CO 3 ) 3 3- was the predominant aqueous neodymium species in 0.1 to 2 M sodium carbonate and 0.1 to 1 M sodium bicarbonate solutions. The logarithm of the NaNd(CO 3 ) 2 x 6 H 2 O solubility product (NaNd(CO 3 ) 2 x 6 H 2 O(c)=Na + +Nd 3+ +2 CO 3 2- +6 H 2 O) was calculated to be -21.39. This model also provided satisfactory interpretation of the solubility data of the analogous Am(III) system in less concentrated carbonate and bicarbonate solutions. (orig.)

  16. Mechanism of μ-conotoxin PIIIA binding to the voltage-gated Na+ channel NaV1.4.

    Directory of Open Access Journals (Sweden)

    Rong Chen

    Full Text Available Several subtypes of voltage-gated Na+ (NaV channels are important targets for pain management. μ-Conotoxins isolated from venoms of cone snails are potent and specific blockers of different NaV channel isoforms. The inhibitory effect of μ-conotoxins on NaV channels has been examined extensively, but the mechanism of toxin specificity has not been understood in detail. Here the known structure of μ-conotoxin PIIIA and a model of the skeletal muscle channel NaV1.4 are used to elucidate elements that contribute to the structural basis of μ-conotoxin binding and specificity. The model of NaV1.4 is constructed based on the crystal structure of the bacterial NaV channel, NaVAb. Six different binding modes, in which the side chain of each of the basic residues carried by the toxin protrudes into the selectivity filter of NaV1.4, are examined in atomic detail using molecular dynamics simulations with explicit solvent. The dissociation constants (Kd computed for two selected binding modes in which Lys9 or Arg14 from the toxin protrudes into the filter of the channel are within 2 fold; both values in close proximity to those determined from dose response data for the block of NaV currents. To explore the mechanism of PIIIA specificity, a double mutant of NaV1.4 mimicking NaV channels resistant to μ-conotoxins and tetrodotoxin is constructed and the binding of PIIIA to this mutant channel examined. The double mutation causes the affinity of PIIIA to reduce by two orders of magnitude.

  17. Muscle K+, Na+, and Cl- disturbances and Na+-K+ pump inactivation: implications for fatigue

    DEFF Research Database (Denmark)

    McKenna, Michael J; Bangsbo, Jens; Renaud, Jean-Marc

    2008-01-01

    (+)-ATPase activity during exercise stabilizes Na(+) and K(+) concentration gradients and membrane excitability and thus protects against fatigue. However, during intense contraction some Na(+)-K(+) pumps are inactivated and together with further ionic disturbances, likely precipitate muscle fatigue.......Membrane excitability is a critical regulatory step in skeletal muscle contraction and is modulated by local ionic concentrations, conductances, ion transporter activities, temperature, and humoral factors. Intense fatiguing contractions induce cellular K(+) efflux and Na(+) and Cl(-) influx......, causing pronounced perturbations in extracellular (interstitial) and intracellular K(+) and Na(+) concentrations. Muscle interstitial K(+) concentration may increase 1- to 2-fold to 11-13 mM and intracellular K(+) concentration fall by 1.3- to 1.7-fold; interstitial Na(+) concentration may decline by 10 m...

  18. Route, mechanism, and implications of proton import during Na+/K+ exchange by native Na+/K+-ATPase pumps

    Science.gov (United States)

    Vedovato, Natascia

    2014-01-01

    A single Na+/K+-ATPase pumps three Na+ outwards and two K+ inwards by alternately exposing ion-binding sites to opposite sides of the membrane in a conformational sequence coupled to pump autophosphorylation from ATP and auto-dephosphorylation. The larger flow of Na+ than K+ generates outward current across the cell membrane. Less well understood is the ability of Na+/K+ pumps to generate an inward current of protons. Originally noted in pumps deprived of external K+ and Na+ ions, as inward current at negative membrane potentials that becomes amplified when external pH is lowered, this proton current is generally viewed as an artifact of those unnatural conditions. We demonstrate here that this inward current also flows at physiological K+ and Na+ concentrations. We show that protons exploit ready reversibility of conformational changes associated with extracellular Na+ release from phosphorylated Na+/K+ pumps. Reversal of a subset of these transitions allows an extracellular proton to bind an acidic side chain and to be subsequently released to the cytoplasm. This back-step of phosphorylated Na+/K+ pumps that enables proton import is not required for completion of the 3 Na+/2 K+ transport cycle. However, the back-step occurs readily during Na+/K+ transport when external K+ ion binding and occlusion are delayed, and it occurs more frequently when lowered extracellular pH raises the probability of protonation of the externally accessible carboxylate side chain. The proton route passes through the Na+-selective binding site III and is distinct from the principal pathway traversed by the majority of transported Na+ and K+ ions that passes through binding site II. The inferred occurrence of Na+/K+ exchange and H+ import during the same conformational cycle of a single molecule identifies the Na+/K+ pump as a hybrid transporter. Whether Na+/K+ pump–mediated proton inflow may have any physiological or pathophysiological significance remains to be clarified. PMID

  19. Route, mechanism, and implications of proton import during Na+/K+ exchange by native Na+/K+-ATPase pumps.

    Science.gov (United States)

    Vedovato, Natascia; Gadsby, David C

    2014-04-01

    A single Na(+)/K(+)-ATPase pumps three Na(+) outwards and two K(+) inwards by alternately exposing ion-binding sites to opposite sides of the membrane in a conformational sequence coupled to pump autophosphorylation from ATP and auto-dephosphorylation. The larger flow of Na(+) than K(+) generates outward current across the cell membrane. Less well understood is the ability of Na(+)/K(+) pumps to generate an inward current of protons. Originally noted in pumps deprived of external K(+) and Na(+) ions, as inward current at negative membrane potentials that becomes amplified when external pH is lowered, this proton current is generally viewed as an artifact of those unnatural conditions. We demonstrate here that this inward current also flows at physiological K(+) and Na(+) concentrations. We show that protons exploit ready reversibility of conformational changes associated with extracellular Na(+) release from phosphorylated Na(+)/K(+) pumps. Reversal of a subset of these transitions allows an extracellular proton to bind an acidic side chain and to be subsequently released to the cytoplasm. This back-step of phosphorylated Na(+)/K(+) pumps that enables proton import is not required for completion of the 3 Na(+)/2 K(+) transport cycle. However, the back-step occurs readily during Na(+)/K(+) transport when external K(+) ion binding and occlusion are delayed, and it occurs more frequently when lowered extracellular pH raises the probability of protonation of the externally accessible carboxylate side chain. The proton route passes through the Na(+)-selective binding site III and is distinct from the principal pathway traversed by the majority of transported Na(+) and K(+) ions that passes through binding site II. The inferred occurrence of Na(+)/K(+) exchange and H(+) import during the same conformational cycle of a single molecule identifies the Na(+)/K(+) pump as a hybrid transporter. Whether Na(+)/K(+) pump-mediated proton inflow may have any physiological or

  20. Growth mechanism of NaClO 3 and NaBrO 3 crystals from aqueous ...

    Indian Academy of Sciences (India)

    A study of growth rates of NaClO3 and NaBrO3 has been carried out using a small growth cell by in situ observation. Normal growth rates of {100} faces of NaClO3 and {111} faces of NaBrO3 along ⟨ 110 ⟩ direction are measured under relatively high supersaturation ranging from 3–8%. In the initial stages of growth, {100}, ...

  1. Rescue of Na+ affinity in aspartate 928 mutants of Na+,K+-ATPase by secondary mutation of glutamate 314.

    Science.gov (United States)

    Holm, Rikke; Einholm, Anja P; Andersen, Jens P; Vilsen, Bente

    2015-04-10

    The Na(+),K(+)-ATPase binds Na(+) at three transport sites denoted I, II, and III, of which site III is Na(+)-specific and suggested to be the first occupied in the cooperative binding process activating phosphorylation from ATP. Here we demonstrate that the asparagine substitution of the aspartate associated with site III found in patients with rapid-onset dystonia parkinsonism or alternating hemiplegia of childhood causes a dramatic reduction of Na(+) affinity in the α1-, α2-, and α3-isoforms of Na(+),K(+)-ATPase, whereas other substitutions of this aspartate are much less disruptive. This is likely due to interference by the amide function of the asparagine side chain with Na(+)-coordinating residues in site III. Remarkably, the Na(+) affinity of site III aspartate to asparagine and alanine mutants is rescued by second-site mutation of a glutamate in the extracellular part of the fourth transmembrane helix, distant to site III. This gain-of-function mutation works without recovery of the lost cooperativity and selectivity of Na(+) binding and does not affect the E1-E2 conformational equilibrium or the maximum phosphorylation rate. Hence, the rescue of Na(+) affinity is likely intrinsic to the Na(+) binding pocket, and the underlying mechanism could be a tightening of Na(+) binding at Na(+) site II, possibly via movement of transmembrane helix four. The second-site mutation also improves Na(+),K(+) pump function in intact cells. Rescue of Na(+) affinity and Na(+) and K(+) transport by second-site mutation is unique in the history of Na(+),K(+)-ATPase and points to new possibilities for treatment of neurological patients carrying Na(+),K(+)-ATPase mutations. © 2015 by The American Society for Biochemistry and Molecular Biology, Inc.

  2. The system NaVO3-Na2WO4-Na2W2O7

    International Nuclear Information System (INIS)

    Kazanbekov, V.R.; Gasanaliev, A.M.; Kazanbekov, R.G.

    1994-01-01

    Phase diagrams of sodium metavanadate-sodium ditungstate, sodium metavanadate-sodium tungstate systems and surface of primary crystallization of sodium metavabadate-sodium tungstate-sodium ditungstate system were studied. The system sodium metavanadate-sodium ditungstate is eutectic one. Compound NaVO 3 x2Na 2 WO 4 is formed in solid state in sodium metavanadate-sodium tungstate system. Liquidus surface of sodium metavanadate-sodium tungstate-sodium ditungstate is presented by three crystallization fields of initial components. Composition and melting point of ternary eutectics are determined

  3. 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.

  4. Summer sudden Na number density enhancements measured with the ALOMAR Weber Na Lidar

    Directory of Open Access Journals (Sweden)

    D. Heinrich

    2008-05-01

    Full Text Available We present summer Na-densities and atmospheric temperatures measured 80 to 110 km above the Arctic Lidar Observatory for Middle Atmosphere Research (ALOMAR. The Weber Na Lidar is part of ALOMAR, located at 69° N in Norway, 150 km north of the Arctic Circle. The sun does not set here during the summer months, and measurements require a narrowband Faraday Anomalous Dispersion Optical Filter (FADOF.

    We discuss an observed sudden enhancement in the Na number density around 22:00 UT on 1 to 2 June 2006. We compare this observation with previous summer measurements and find a frequent appearance of Na number density enhancements near local midnight. We describe the time of appearance, the altitude distribution, the duration and the strength of these enhancements and compare them to winter observations. We investigate possible formation mechanisms and, as others before, we find a strong link between these Na number density enhancements and sporadic E layers.

  5. Summer sudden Na number density enhancements measured with the ALOMAR Weber Na Lidar

    Directory of Open Access Journals (Sweden)

    D. Heinrich

    2008-05-01

    Full Text Available We present summer Na-densities and atmospheric temperatures measured 80 to 110 km above the Arctic Lidar Observatory for Middle Atmosphere Research (ALOMAR. The Weber Na Lidar is part of ALOMAR, located at 69° N in Norway, 150 km north of the Arctic Circle. The sun does not set here during the summer months, and measurements require a narrowband Faraday Anomalous Dispersion Optical Filter (FADOF. We discuss an observed sudden enhancement in the Na number density around 22:00 UT on 1 to 2 June 2006. We compare this observation with previous summer measurements and find a frequent appearance of Na number density enhancements near local midnight. We describe the time of appearance, the altitude distribution, the duration and the strength of these enhancements and compare them to winter observations. We investigate possible formation mechanisms and, as others before, we find a strong link between these Na number density enhancements and sporadic E layers.

  6. Muziki wa Hip Hop na Haki Za Kijamii: Dhima, Changamoto na ...

    African Journals Online (AJOL)

    Ni dhahiri kuwa haki za kijamii zinaweza kuwasilishwa kwa jamii pana kupitia sanaa ya hip hop. Makala haya basi, yanabainisha dhima na mchango wa muziki wa hip hop katika masuala ya haki za kijamii, yanafafanua changamoto za muziki huu katika kuwasilisha haki za kijamii na kutoa mapendekezo kwa makundi ...

  7. Sequential growth of sandwiched NaYF{sub 4}:Yb/Er@NaYF{sub 4}:Yb@NaNdF{sub 4}:Yb core–shell–shell nanoparticles for photodynamic therapy

    Energy Technology Data Exchange (ETDEWEB)

    Peng, Huang-Yong; Ding, Bin-Bin; Ma, Yin-Chu [Department of Medical Materials and Rehabilitation Engineering, School of Medical Engineering, Hefei University of Technology, Hefei 230009 (China); Sun, Shi-Qi [State Key Laboratory of Veterinary Etiological Biology and Key Laboratory of Animal Virology of Ministry of Agriculture, Lanzhou Veterinary Research Institute, Chinese Academy of Agricultural Sciences, Xujiaping 1, Lanzhou, Gansu 730046 (China); Tao, Wei [Department of Medical Materials and Rehabilitation Engineering, School of Medical Engineering, Hefei University of Technology, Hefei 230009 (China); Guo, Yan-Chuan [Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, Beijing 100190 (China); Guo, Hui-Chen, E-mail: ghch-2004@hotmail.com [State Key Laboratory of Veterinary Etiological Biology and Key Laboratory of Animal Virology of Ministry of Agriculture, Lanzhou Veterinary Research Institute, Chinese Academy of Agricultural Sciences, Xujiaping 1, Lanzhou, Gansu 730046 (China); Yang, Xian-Zhu, E-mail: yangxz@hftu.edu.cn [Department of Medical Materials and Rehabilitation Engineering, School of Medical Engineering, Hefei University of Technology, Hefei 230009 (China); Qian, Hai-Sheng, E-mail: shqian@hfut.edu.cn [Department of Medical Materials and Rehabilitation Engineering, School of Medical Engineering, Hefei University of Technology, Hefei 230009 (China)

    2015-12-01

    Graphical abstract: The monodisperse elliptical NaYF{sub 4}:Yb/Er@NaYF{sub 4}:Yb@NaNdF{sub 4}:Yb core–shell–shell nanoparticles have been synthesized successfully by a facile sequential growth process, which can be used as transducer for photodynamic therapy of cancer cells. - Highlights: • The NaYF{sub 4}:Yb/Er@NaYF{sub 4}:Yb@NaNdF{sub 4}:Yb nanoparticles have been fabricated successfully. • The as-prepared nanoparticles show strong fluorescence excited at 980 or 808 nm. • The nanoparticles were transferred into the aqueous phase via a facile process. • Photosensitizers were loaded into the composites for photodynamic therapy. - Abstract: Upconversion (UC) nanostructures have attracted much interest for their extensive biological applications. In this work, we describe a sequential synthetic route to prepare sandwiched NaYF{sub 4}:Yb/Er@NaYF{sub 4}:Yb@NaNdF{sub 4}:Yb core–shell upconversion nanoparticles. The as-prepared products were investigated by X-ray diffraction (XRD) and transmission electron microscopy (TEM, JEM 2100F), respectively. The as-prepared core–shell nanoparticles of NaYF{sub 4}:Yb/Er@NaYF{sub 4}:Yb@NaNdF{sub 4}:Yb are composed of elliptical nanoparticles with a length of 80 nm and width of 42 nm, which show efficient upconversion fluorescence excited at 808 nm indicating the formation of core–shell–shell sandwiched nanostructures. In addition, the as-prepared sandwiched NaYF{sub 4}:Yb/Er@NaYF{sub 4}:Yb@NaNdF{sub 4}:Yb core–shell upconversion nanoparticles also show strong upconversion fluorescence excited at 980 nm. Amphiphilic mPEG{sub 2k}-b-PEBEP{sub 6K} copolymers (denoted as PPE) were chosen to transfer these hydrophobic UCNPs into the aqueous phase for biological application. In vitro photodynamic therapy of cancer cells show that the viability of cells incubated with the nanoparticles loaded with MC 540 was significantly lower as compared to the nanoparticles without photosensitizers exposed to NIR laser.

  8. Intracellular Na+ regulation of Na+ pump sites in cultured vascular smooth muscle cells

    International Nuclear Information System (INIS)

    Allen, J.C.; Navran, S.S.; Seidel, C.L.; Dennison, D.K.; Amann, J.M.; Jemelka, S.K.

    1989-01-01

    Enzymatically dispersed cells from canine saphenous vein and femoral artery were grown in fetal calf serum and studied at day 0 (freshly dispersed) through confluence in primary culture. Intracellular Na levels (Nai), but not intracellular K (Ki), were increased after 24 h in culture and then decreased to a steady state by 4 days. Na+ pump site number [( 3 H] ouabain binding) increased through day 3 and remained elevated. Nai was still elevated at 2 days when the Na+ pump site number began to increase. Total pump turnover (maximum ouabain-inhibited 86 Rb uptake) reflected the increase in Na+ pump site number. These key events precede the observed increases in both protein production and cellular proliferation. If the same cells are maintained in defined medium, without fetal calf serum, Nai, Ki, and the number of [ 3 H]ouabain binding sites do not change with time. These data are consistent with the suggestion that the initial mitogenic response of vascular smooth muscle cells to fetal calf serum involves an increased Na+ influx, and a Nai accumulation, caused by low Na+ pump density. The synthesis of new pump sites effects a decrease in the accumulated Nai, which may be related to cell proliferation

  9. On the Stability of NaO2 in Na-O2 Batteries.

    Science.gov (United States)

    Liu, Chenjuan; Carboni, Marco; Brant, William R; Pan, Ruijun; Hedman, Jonas; Zhu, Jiefang; Gustafsson, Torbjörn; Younesi, Reza

    2018-04-25

    Na-O 2 batteries are regarded as promising candidates for energy storage. They have higher energy efficiency, rate capability, and chemical reversibility than Li-O 2 batteries; in addition, sodium is cheaper and more abundant compared to lithium. However, inconsistent observations and instability of discharge products have inhibited the understanding of the working mechanism of this technology. In this work, we have investigated a number of factors that influence the stability of the discharge products. By means of in operando powder X-ray diffraction study, the influence of oxygen, sodium anode, salt, solvent, and carbon cathode were investigated. The Na metal anode and an ether-based solvent are the main factors that lead to the instability and decomposition of NaO 2 in the cell environment. This fundamental insight brings new information on the working mechanism of Na-O 2 batteries.

  10. NaK handling and removal

    International Nuclear Information System (INIS)

    Desreumaux, J.; Rodriguez, G.; Guigon, A.; Verdelli, J.; Thomine, G.

    1997-01-01

    Sodium-potassium alloy is used in specific application in French Fast Breeder Reactors as: cold traps, NaK bubbler for argon purification, valves and also in experimental irradiation devices. lt has been preferred to sodium because it is liquid from + 7 deg. C for the most common peritectic alloy. After its use, NaK is considered as a hazardous waste (nuclear or not) due to its high reactivity with air and water. The most important risk remains in handling NaK systems which have not been operated for some time. The NaK will be covered with a crust of the superoxide K02 which is a strong oxidising agent. Thermodynamically, K02 will react with most organic material or metallic dust or swarfs and can also react with additional NaK to give sufficient heat to boil part of the NaK, resulting in a sudden increase in pressure and small explosions. We describe the formation given to experimenters in our Sodium School and the CEA's experience in treating specific devices for transportation, decanting of tanks, tank opening and NaK removal. (author)

  11. Angiotensin II-induced hypertension increases plasma membrane Na pump activity by enhancing Na entry in rat thick ascending limbs.

    Science.gov (United States)

    Gonzalez-Vicente, Agustin; Garvin, Jeffrey L

    2013-11-01

    Thick ascending limbs (TAL) reabsorb 30% of the filtered NaCl load. Na enters the cells via apical Na-K-2Cl cotransporters and Na/H exchangers and exits via basolateral Na pumps. Chronic angiotensin II (ANG II) infusion increases net TAL Na transport and Na apical entry; however, little is known about its effects on the basolateral Na pump. We hypothesized that in rat TALs Na pump activity is enhanced by ANG II-infusion, a model of ANG II-induced hypertension. Rats were infused with 200 ng·kg(-1)·min(-1) ANG II or vehicle for 7 days, and TAL suspensions were obtained. We studied plasma membrane Na pump activity by measuring changes in 1) intracellular Na (Nai) induced by ouabain; and 2) ouabain-sensitive oxygen consumption (QO2). We found that the ouabain-sensitive rise in Nai in TALs from ANG II-infused rats was 12.8 ± 0.4 arbitrary fluorescent units (AFU)·mg(-1)·min(-1) compared with only 9.9 ± 1.1 AFU·mg(-1)·min(-1) in controls (P Na pump expression, the number of Na pumps in the plasma membrane, or the affinity for Na. When furosemide (1.1 mg·kg(-1)·day(-1)) was coinfused with ANG II, no increase in plasma membrane Na pump activity was observed. We concluded that in ANG II-induced hypertension Na pump activity is increased in the plasma membrane of TALs and that this increase is caused by the chronically enhanced Na entry occurring in this model.

  12. Silicene for Na-ion battery applications

    KAUST Repository

    Zhu, Jiajie

    2016-08-19

    Na-ion batteries are promising candidates to replace Li-ion batteries in large scale applications because of the advantages in natural abundance and cost of Na. Silicene has potential as the anode in Li-ion batteries but so far has not received attention with respect to Na-ion batteries. In this context, freestanding silicene, a graphene-silicene-graphene heterostructure, and a graphene-silicene superlattice are investigated for possible application in Na-ion batteries, using first-principles calculations. The calculated Na capacities of 954mAh/g for freestanding silicene and 730mAh/g for the graphenesilicene superlattice (10% biaxial tensile strain) are highly competitive and potentials of >0.3 V against the Na/Na potential exceed the corresponding value of graphite. In addition, the diffusion barriers are predicted to be <0.3 eV.

  13. Hydrolysis of Rice Straw Pretreated by Na2SO3 Over Fe-resin/NaCl

    Directory of Open Access Journals (Sweden)

    YANG Hui

    2017-05-01

    Full Text Available To increase the conversion of rice straw(RS and the yield of products, we employed three methods, which were ultrasonic wave, steam explosion and Na2SO3 pretreatment to pretreat RS(the treated RS noted as CS-RS, ZQ-RS and Na2SO3-RS, respectively and found that Na2SO3 treatment was the best pretreatment method based on XRD, SEM, elemental analysis and content of cellulose, hemicellulose and lignin. The conversion of Na2SO3-RS and the yield of total reducing sugar(TRS and levulinic acid(LA were 97.3%, 29.6% and 13.5%, respectively by 10% Fe-resin in 3.3% NaCl solution under 200 ℃.

  14. Na+/H+ and Na+/NH4+ exchange activities of zebrafish NHE3b expressed in Xenopus oocytes

    Science.gov (United States)

    Ito, Yusuke; Kato, Akira; Hirata, Taku; Hirose, Shigehisa

    2014-01-01

    Zebrafish Na+/H+ exchanger 3b (zNHE3b) is highly expressed in the apical membrane of ionocytes where Na+ is absorbed from ion-poor fresh water against a concentration gradient. Much in vivo data indicated that zNHE3b is involved in Na+ absorption but not leakage. However, zNHE3b-mediated Na+ absorption has not been thermodynamically explained, and zNHE3b activity has not been measured. To address this issue, we overexpressed zNHE3b in Xenopus oocytes and characterized its activity by electrophysiology. Exposure of zNHE3b oocytes to Na+-free media resulted in significant decrease in intracellular pH (pHi) and intracellular Na+ activity (aNai). aNai increased significantly when the cytoplasm was acidified by media containing CO2-HCO3− or butyrate. Activity of zNHE3b was inhibited by amiloride or 5-ethylisopropyl amiloride (EIPA). Although the activity was accompanied by a large hyperpolarization of ∼50 mV, voltage-clamp experiments showed that Na+/H+ exchange activity of zNHE3b is electroneutral. Exposure of zNHE3b oocytes to medium containing NH3/NH4+ resulted in significant decreases in pHi and aNai and significant increase in intracellular NH4+ activity, indicating that zNHE3b mediates the Na+/NH4+ exchange. In low-Na+ (0.5 mM) media, zNHE3b oocytes maintained aNai of 1.3 mM, and Na+-influx was observed when pHi was decreased by media containing CO2-HCO3− or butyrate. These results provide thermodynamic evidence that zNHE3b mediates Na+ absorption from ion-poor fresh water by its Na+/H+ and Na+/NH4+ exchange activities. PMID:24401990

  15. The relation between aging, aortic NaF avidity and coronary artery NaF avidity: A NaF PET CT study

    DEFF Research Database (Denmark)

    Blomberg, Björn; Thomassen, Anders; Hildebrandt, Malene

    2013-01-01

    volunteers without traditional cardiovascular risk factors were prospectively assessed by Sodium 18-Fluoride (Na-18F) PET CT imaging. Global aortic uptake of Na-18F was determined by calculating the average aortic blood pool subtracted maximum standardized uptake value (cSUV) [maximum SUVaorta - mean...

  16. 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)

  17. Rescue of Na+ and H+ binding in Na+,K+-ATPase M8 aspartate mutants by secondary mutation

    DEFF Research Database (Denmark)

    Holm, Rikke; Einholm, Anja P.; Andersen, Jens Peter

    A mutation replacing the aspartate in transmembrane segment M8 in the a3-isoform of Na,K-ATPase with asparagine has been found in patients with rapid-onset dystonia parkinsonism or alternating hemiplegia of childhood. This aspartate may be a critical Na+ coordinating residue, but the crystal......-isoforms of Na,K-ATPase, and much smaller effects were seen for other mutations to the M8 aspartate, which were less disruptive of Na+ binding than mutations to other residues related to Na+ site III. The D928 (rat a1 numbering) mutations strongly diminished the cooperativity of Na+ binding. Moreover the p......H optimum of Na,K-ATPase activity was left-shifted, again with D928N being most disruptive. The reduced affinity for activating Na+ and for inhibitory protons, caused by D928N and D928A mutations, could be rescued by introduction of an additional mutation of a glutamate located far away from D928....

  18. Salinity tolerance in barley (hordeum vulgare l.): effects of varying NaCl, K/sup +/ Na/sup +/ and NaHCO/sub 3/ levels on cultivars differing in tolerance

    International Nuclear Information System (INIS)

    Mahmood, K.

    2011-01-01

    Although barley (Hordeum vulgare L.) is regarded as salt tolerant among crop plants, its growth and plant development is severely affected by ionic and osmotic stresses in salt-affected soils. To elucidate the tolerance mechanism, growth and ion uptake of three barley cultivars, differing in salt tolerance, were examined under different levels of NaCl, K/sup +/ Na/sup +/ and NaHCO/sub 3/ in the root medium. The cultivars differed greatly in their responses to varying root medium conditions. Plant growth was more adversely affected by NaHCO/sub 3/ than NaCl. In general, biomass yields were comparable under control and 100 mM NaCl. However, growth of all three cultivars was significantly inhibited by NaHCO/sub 3/ even at low concentration (10 mM). Improved K/sup +/ supply in saline medium increased K/sup +/ uptake and growth of less tolerant cultivars. K/sup +/ uptake was more adversely affected by NaHCO/sub 3/ than NaCl salinity. Selective K/sup +/ uptake and lower Cl/sup -/ in shoots seemed to be associated with the growth responses. K application would help better growth of these cultivars on K-deficient saline-sodic soils and under irrigation with poor quality water having high Residual Sodium Carbonate (RSC) and/or Sodium Adsorption Ratio (SAR). (author)

  19. Glutathionylation-Dependence of Na+-K+-Pump Currents Can Mimic Reduced Subsarcolemmal Na+ Diffusion

    OpenAIRE

    Garcia, Alvaro; Liu, Chia-Chi; Cornelius, Flemming; Clarke, Ronald?J.; Rasmussen, Helge?H.

    2016-01-01

    The existence of a subsarcolemmal space with restricted diffusion for Na+ in cardiac myocytes has been inferred from a transient peak electrogenic Na+-K+ pump current beyond steady state on reexposure of myocytes to K+ after a period of exposure to K+-free extracellular solution. The transient peak current is attributed to enhanced electrogenic pumping of Na+ that accumulated in the diffusion-restricted space during pump inhibition in K+-free extracellular solution. However, there are no know...

  20. Myocardial Na,K-ATPase: Clinical aspects

    OpenAIRE

    Kjeldsen, Keld

    2003-01-01

    The specific binding of digitalis glycosides to Na,K-ATPase is used as a tool for Na,K-ATPase quantification with high accuracy and precision. In myocardial biopsies from patients with heart failure, total Na,K-ATPase concentration is decreased by around 40%; a correlation exists between a decrease in heart function and a decrease in Na,K-ATPase concentration. During digitalization, around 30% of remaining pumps are occupied by digoxin. Myocardial Na,K-ATPase is also influenced by other drugs...

  1. Down-Regulation of the Na+-Coupled Phosphate Transporter NaPi-IIa by AMP-Activated Protein Kinase

    Directory of Open Access Journals (Sweden)

    Miribane Dërmaku-Sopjani

    2013-11-01

    Full Text Available Background/Aims: The Na+-coupled phosphate transporter NaPi-IIa is the main carrier accomplishing renal tubular phosphate reabsorption. It is driven by the electrochemical Na+ gradient across the apical cell membrane, which is maintained by Na+ extrusion across the basolateral cell membrane through the Na+/K+ ATPase. The operation of NaPi-IIa thus requires energy in order to avoid cellular Na+ accumulation and K+ loss with eventual decrease of cell membrane potential, Cl- entry and cell swelling. Upon energy depletion, early inhibition of Na+-coupled transport processes may delay cell swelling and thus foster cell survival. Energy depletion is sensed by the AMP-activated protein kinase (AMPK, a serine/threonine kinase stimulating several cellular mechanisms increasing energy production and limiting energy utilization. The present study explored whether AMPK influences the activity of NAPi-IIa. Methods: cRNA encoding NAPi-IIa was injected into Xenopus oocytes with or without additional expression of wild-type AMPK (AMPKα1-HA+AMPKβ1-Flag+AMPKγ1-HA, of inactive AMPKαK45R (AMPKα1K45R+AMPKβ1-Flag+AMPKγ1-HA or of constitutively active AMPKγR70Q (AMPKα1-HA+AMPKβ1-Flag+AMPKγ1R70Q. NaPi-IIa activity was estimated from phosphate-induced current in dual electrode voltage clamp experiments. Results: In NaPi-IIa-expressing, but not in water-injected Xenopus oocytes, the addition of phosphate (1 mM to the extracellular bath solution generated a current (Ip, which was significantly decreased by coexpression of wild-type AMPK and of AMPKγR70Q but not of AMPKαK45R. The phosphate-induced current in NaPi-IIa- and AMPK-expressing Xenopus ooocytes was significantly increased by AMPK inhibitor Compound C (20 µM. Kinetic analysis revealed that AMPK significantly decreased the maximal transport rate. Conclusion: The AMP-activated protein kinase AMPK is a powerful regulator of NaPi-IIa and thus of renal tubular phosphate transport.

  2. Thermodynamic study of NaFe complex oxides. High temperature properties of Na sub 5 FeO sub 4 and Na sub 3 FeO sub 3

    CERN Document Server

    Furukawa, T

    2002-01-01

    In order to contribute the investigation into corrosion mechanism of the structural materials by leakage sodium, thermodynamic study of Na-Fe complex oxides formed by the reactions was carried out. Na sub 5 FeO sub 4 and Na sub 3 FeO sub 3 were used as the sample. Its high temperature properties (i.e. melting, solidification and transformation) were observed by Differential Scanning Calorimetry, DSC. Moreover, the original test named 'melting point confirmation test' was performed for the observation of traces of melting and solidification after the tests. Following contents have been obtained by this study. (1) Na sub 5 FeO sub 4 was stably as the solid without phase transformation and melting until 800degC. However, the compound was showing a tendency to change into Na sub 4 FeO sub 3 with temperature increasing under the low oxygen potential. (2) The stability of Na sub 3 FeO sub 3 is the same as that of Na sub 5 FeO sub 4 until 700degC. Over the temperature, the compound was changed differential compound ...

  3. Metallic Na formation in NaCl crystals with irradiation of electron or vacuum ultraviolet photon

    Energy Technology Data Exchange (ETDEWEB)

    Owaki, Shigehiro [Osaka Prefecture Univ., Sakai, Osaka (Japan). Coll. of Integrated Arts and Sciences; Koyama, Shigeko; Takahashi, Masao; Kamada, Masao; Suzuki, Ryouichi

    1997-03-01

    Metallic Na was formed in NaCl single crystals with irradiation of a variety of radiation sources and analyzed the physical states with several methods. In the case of irradiation of 21 MeV electron pulses to the crystal blocks, the optical absorption and lifetime measurement of positron annihilation indicated appearance of Na clusters inside. Radiation effects of electron beam of 30 keV to the crystals in vacuum showed the appearance of not only metallic Na but atomic one during irradiation with Auger electron spectroscopy. Intense photon fluxes in vacuum ultraviolet region of synchrotron radiation were used as another source and an analyzing method of ultraviolet photoelectron spectroscopy. The results showed the metallic Na layered so thick that bulk plasmon can exist. (author)

  4. Scintillation efficiency measurement of Na recoils in NaI(Tl) below the DAMA/LIBRA energy threshold

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Jingke; Shields, Emily; Calaprice, Frank; Westerdale, Shawn; Froborg, Francis; Suerfu, Burkhant; Alexander, Thomas; Aprahamian, Ani; Back, Henning O.; Casarella, Clark; Fang, Xiao; Gupta, Yogesh K.; Ianni, Aldo; Lamere, Edward; Lippincott, W. Hugh; Liu, Qian; Lyons, Stephanie; Siegl, Kevin; Smith, Mallory; Tan, Wanpeng; Kolk, Bryant Vande

    2015-07-01

    The dark matter interpretation of the DAMA modulation signal depends on the NaI(Tl) scintillation efficiency of nuclear recoils. Previous measurements for Na recoils have large discrepancies, especially in the DAMA/LIBRA modulation energy region. We report a quenching effect measurement of Na recoils in NaI(Tl) from 3 to 52 keVnr, covering the whole DAMA/LIBRA energy region for dark matter-Na scattering interpretations. By using a low-energy, pulsed neutron beam, a double time-of-flight technique, and pulse-shape discrimination methods, we obtained the most accurate measurement of this kind for NaI(Tl) to date. The results differ significantly from the DAMA reported values at low energies but fall between the other previous measurements. We present the implications of the new quenching results for the dark matter interpretation of the DAMA modulation signal.

  5. Synthesis of Ag or Pt Nanoparticles by Hydrolysis of Either Ag2Na or PtNa

    Directory of Open Access Journals (Sweden)

    Huabin Wang

    2008-01-01

    Full Text Available Ag and Pt nanoparticles have successfully been synthesized by hydrolysis of either Ag2Na or PtNa at room temperature. The oxidation of sodium in the Pt-Na pellets was much faster than that in the Ag-Na pellets since Pt is a catalyst for H2O formation reaction from hydrogen and oxygen at room temperature. The hydrolysis byproduct, NaOH, has a high solubility and easily is removed. This method offers a simple method of preparing transition metal nanoparticles. The Ag and Pt nanoparticles prepared by this method were crystalline in nature, and spherical in shape with a mean size of around 10 nm.

  6. Dynamic polarizabilities and Van der Waals coefficients for alkali atoms Li, Na and alkali dimer molecules Li2, Na2 and NaLi

    Science.gov (United States)

    Mérawa, M.; Dargelos, A.

    1998-07-01

    The present paper gives an account of investigations of the polarizability of the alkali atoms Li, Na, diatomics homonuclear and heteronuclear Li2, Na2 and NaLi at SCF (Self Consistent Field) level of approximation and at correlated level, using a time Time-Dependent Gauge Invariant method (TDGI). Our static polarizability values agree with the best experimental and theoretical determinations. The Van der Waals C6 coefficients for the atom-atom, atom-dimer and dimer-dimer interactions have been evaluated. Les polarisabilités des atomes alcalins Li, Na, et des molécules diatomiques homonucléaires et hétéronucléaire Li2, Na2 et NaLi, ont été calculées au niveau SCF (Self Consistent Field) et au niveau corrélé à partir d'une méthode invariante de jauge dépendante du temps(TDGI). Nos valeurs des polarisabilités statiques sont en accord avec les meilleurs déterminations expérimentales et théoriques. Les coefficients C6 de Van de Waals pour les interactions atome-atome, atome-dimère et dimère-dimère ont également été évalués.

  7. Structure-function relationships of Na+, K+, ATP, or Mg2+ binding and energy transduction in Na,K-ATPase

    DEFF Research Database (Denmark)

    Jorgensen, Peter L.; Pedersen, Per Amstrup

    2000-01-01

    Na,K-ATPase; Mutagenesis; Na+ binding; K+ binding; Tl+ binding; Mg2+ binding; ATP binding; Cation binding site; Energy transduction......Na,K-ATPase; Mutagenesis; Na+ binding; K+ binding; Tl+ binding; Mg2+ binding; ATP binding; Cation binding site; Energy transduction...

  8. At NA2

    CERN Multimedia

    1977-01-01

    One of the NA2 calorimeter sections is moved in. The NA2 calorimeter was divided in two halves, to the left and the right of the beam, each half consisting of sheets of passive high Z material interleaved with blades of plastic scintillators. The photo shows on the right, the upstream 'electron' module with eleven lead plates for a total radiation length of 20.

  9. Na+-K+ pump in chronic renal failure

    International Nuclear Information System (INIS)

    Deepak, K.; Kahn, T.

    1987-01-01

    This review summarizes the evidence for the defect in Na + -K + pump in chronic renal failure, considers the role of various factors in causing this defect, and discusses the clinical implications thereof. Intracellular Na is elevated in erythrocytes, leukocytes, and muscle cells from some patients with chronic renal failure (CRF). Recent evidence suggest that this elevation of cell Na may be, in large part, a consequence of decreased number of Na + -K + pump units per cell. Maintenance dialysis over a period of weeks ameliorates the defect in intracellular Na + , and this improvement is contemporaneous with an increase in the number of Na + -K + pump sites per cell. In erythrocytes with normal cell Na + , acute hemodialysis increases the rate of 22 Na + and 42 K + transport. Many factors such as the presence of retained toxic metabolite or circulating inhibitor in the uremic plasma, or biochemical changes produced by acute hemodialysis, may explain this finding. In cells with high cell Na + , the pump-mediated 42 K + transport is normalized at the expense of a raised cell Na + . The decreased muscle membrane potential in uremic subjects has been attributed to a decreased activity of Na + -K + pump. The authors discuss the role of hormonal abnormalities and circulating inhibitors, which may cause an acute inhibition of the pump and of other factors such as K + depletion, which may cause more chronic alterations. The implications of alteration of Na + and K + pump transport and raised cell Na + on other non-pump-mediated transport pathways are discussed. Raised cell Na + may be a marker for the adequacy of maintenance dialysis in patients with end-stage renal failure

  10. Pozitivni in negativni vplivi risank na otroke

    OpenAIRE

    Povše, Nika

    2017-01-01

    V tej diplomski nalogi smo raziskovali pozitivne in negativne vplive risank na otroke. Začeli smo z zgodovino televizije, tako svetovno zgodovino kot zgodovino televizije na Slovenskem. Na isti način smo pregledali tudi zgodovino risank. Raziskovali smo otrokov razvoj, predvsem tiste vidike, ki so izpostavljeni vplivom risank, kot so morala, jezik, domišljija in učenje. Sledilo je raziskovanje negativnih in pozitivnih vplivov, ki jih imajo risanke na otroke, kar je tudi naš glavni problem te ...

  11. Vpliv konfucija na sodobno izobraževanje na Kitajskem

    Directory of Open Access Journals (Sweden)

    Katja Skitek

    2009-12-01

    Full Text Available Izobraževanje na Kitajskem je bilo vedno trdno povezano s Konfucijem in konfucianizmom, kar pa ni čudno, saj je bil Konfucij prvi, ki je poudarjal moč z nanja in izobraževanja. LR Kitajska je v zadnjih petdesetih letih počasi in postopoma začela uveljavljati določene spremembe v vzgojno-izobraževalni sistem. Kakšne so te spremembe in koliko nanje še vedno vpliva konfucianizem, bo osrednja tema pričujočega članka. Konfucianizem danes na Kitajskem ni preveč popularen, izobraženci pa so se razporedili v dve skupini: eni trdijo, da je njegov vpliv še vedno velik, drugi pa zatrjujejo, da nima več nobenega vpliva na sodobno življenje. Katera stran ima prav? Konfucij je v prvi vrsti poudarjal pomembnost moralnih vrednot vsakega človeka in prav moralne vrednote, za katere se je zavzemal, so še danes trdno zasidrane v kitajski kulturi. Ali je torej sploh mogoče popolnoma izriniti Konfucija iz sodobnega izobraževanja?

  12. Low-spin states of 23Na

    International Nuclear Information System (INIS)

    Bakkum, E.L.

    1987-01-01

    A study of 23 Na via the 22 Ne(p,γ) 23 Na and 23 Na(γ,γ) 23 Na reactions is presented. Only a limited number of resonances has been studied, selected on the basis of strong excitation of the lowest levels of which the spin was unknown. As a result the spins are now known of all levels of 23 Na with excitation energies up to 7 MeV, except for a few high-spin states which are too weakly excited in the decay of the known 22 Ne(p,γ) resonances. The mean lifetimes of the 23 Na levels at 4.43 and 7.89 MeV were found to be 350±70 and 220±17 attoseconds (1 attosecond = 10 -18 seconds) respectively. 97 refs.; 22 figs.; 12 tabs

  13. Response of saliva Na/K ratio to changing Na supply of lactating cows under tropical conditions

    NARCIS (Netherlands)

    Thiangtum, Wandee; Schonewille, J Thomas; Verstegen, Martin Wa; Arsawakulsudhi, Supot; Rukkwamsuk, Theera; Hendriks, Wouter H

    BACKGROUND: Factorial determination of the sodium (Na) requirement of heat-stressed lactating cows is hindered by accurate estimates of the Na losses through sweat. Direct studies, therefore, may be needed requiring information on the time course of healthy animals to become Na depleted and the

  14. Response of saliva Na/K ratio to changing Na supply of lactating cows under tropical conditions

    NARCIS (Netherlands)

    Thiangtum, Wandee; Schonewille, Thomas J.; Verstegen, Martin W.A.; Arsawakulsudhi, Supot; Rukkwamsuk, Theera; Hendriks, Wouter H.

    2017-01-01

    BACKGROUND: Factorial determination of the sodium (Na) requirement of heat-stressed lactating cows is hindered by accurate estimates of the Na losses through sweat. Direct studies, therefore, may be needed requiring information on the time course of healthy animals to become Na depleted and the

  15. Clues to NaCN formation

    Science.gov (United States)

    Quintana-Lacaci, G.; Cernicharo, J.; Velilla Prieto, L.; Agúndez, M.; Castro-Carrizo, A.; Fonfría, J. P.; Massalkhi, S.; Pardo, J. R.

    2017-11-01

    Context. ALMA is providing us essential information on where certain molecules form. Observing where these molecules emission arises from, the physical conditions of the gas, and how this relates with the presence of other species allows us to understand the formation of many species, and to significantly improve our knowledge of the chemistry that occurs in the space. Aims: We studied the molecular distribution of NaCN around IRC +10216, a molecule detected previously, but whose origin is not clear. High angular resolution maps allow us to model the abundance distribution of this molecule and check suggested formation paths. Methods: We modeled the emission of NaCN assuming local thermal equilibrium (LTE) conditions. These profiles were fitted to azimuthal averaged intensity profiles to obtain an abundance distribution of NaCN. Results: We found that the presence of NaCN seems compatible with the presence of CN, probably as a result of the photodissociation of HCN, in the inner layers of the ejecta of IRC +10216. However, similar as for CH3CN, current photochemical models fail to reproduce this CN reservoir. We also found that the abundance peak of NaCN appears at a radius of 3 × 1015 cm, approximately where the abundance of NaCl, suggested to be the parent species, starts to decay. However, the abundance ratio shows that the NaCl abundance is lower than that obtained for NaCN. We expect that the LTE assumption might result in NaCN abundances higher than the real ones. Updated photochemical models, collisional rates, and reaction rates are essential to determine the possible paths of the NaCN formation. Based on observations carried out with ALMA and the IRAM 30 m Telescope. ALMA is a partnership of ESO (representing its member states), NSF (USA) and NINS (Japan), together with NRC (Canada) and NSC and ASIAA (Taiwan), in cooperation with the Republic of Chile. The Joint ALMA Observatory is operated by ESO, AUI/NRAO and NAOJ. IRAM is supported by INSU/CNRS (France

  16. The effect of Na+ and K+ on the thermal denaturation of Na+ and + K+-dependent ATPase.

    Science.gov (United States)

    Fischer, T H

    1983-01-01

    To increase our understanding of the physical nature of the Na+ and K+ forms of the Na+ + K+-dependent ATPase, thermal-denaturation studies were conducted in different types of ionic media. Thermal-denaturation measurements were performed by measuring the regeneration of ATPase activity after slow pulse exposure to elevated temperatures. Two types of experiments were performed. First, the dependence of the thermal-denaturation rate on Na+ and K+ concentrations was examined. It was found that both cations stabilized the pump protein. Also, K+ was a more effective stabilizer of the native state than was Na+. Secondly, a set of thermodynamic parameters was obtained by measuring the temperature-dependence of the thermal-denaturation rate under three ionic conditions: 60 mM-K+, 150 mM-Na+ and no Na+ or K+. It was found that ion-mediated stabilization of the pump protein was accompanied by substantial increases in activation enthalpy and entropy, the net effect being a less-pronounced increase in activation free energy. PMID:6309139

  17. Financiranje projekata na pomorskom dobru

    Directory of Open Access Journals (Sweden)

    Zoran Tasić

    2018-02-01

    Full Text Available Koncesije otvaraju vrlo osjetljiva politička, ekonomska i pravna pitanja u mnogim državama svijeta. Samo definiranje pojma koncesije često je komplicirana i ne sasvim jasna zadaća. OECD je prihvatila definiciju koncesije kao: ’’davanje prava privatnom trgovačkom društvu da može gospodarski upravljati određenom infrastrukturnim uslugama i za to zarađivati naknadu. Koncesionar dobija u posjed određene objekte (ali vlasništvo na tim objektima ostaje u rukama države te ih koristi u svrhu obavljanja određene djelatnosti ili usluge sukladno odredbama ugovora’’. Hrvatsko pravo definira koncesije načelno kao pravo stečeno temeljem ugovora o koncesiji, a sukladno uvjetima sadržanim u odluci o davanju koncesije (koju je donijelo odgovarajuće upravno tijelo, a u odnosu na pomorsko dobro, specifično, kao pravo državne vlasti da može dio pomorskog dobra, koje je inače dobro izvan pravnog prometa (res extra commercium, isključiti iz opće uporabe bilo dijelom ili u cijelosti, i dati ga fizičkoj ili pravnoj osobi na gospodarsko korištenje sukladno određenim prostornim planovima. Građevine i drugi objekti izgrađeni na pomorskom dobru čine njegov sastavni dio. Zakonom je jasno određeno da nikakva stvarna prava nisu dopuštena na pomorskom dobru, uključivo i na objektima izgrađenima na njemu. Projekti na pomorskom dobru često uključuju velike infrastrukturne projekte, razvoje luka i marina, koji iziskuju značajna financijska sredstva. Banke koje financiraju takve projekte zahtijevaju organiziran i transparentan zakonski okvir koncesija, slobodu ugovaranja, pravnu zaštitu svih strana uključenih u projekt (uključivo i mogućnost međunarodne arbitraže. (...

  18. Controlled phase stability of highly Na-active triclinic structure in nanoscale high-voltage Na2-2xCo1+xP2O7 cathode for Na-ion batteries

    Science.gov (United States)

    Song, Hee Jo; Kim, Jae-Chan; Dar, Mushtaq Ahmad; Kim, Dong-Wan

    2018-02-01

    With the increasing demand for high energy density in energy-storage systems, a high-voltage cathode is essential in rechargeable Li-ion and Na-ion batteries. The operating voltage of a triclinic-polymorph Na2CoP2O7, also known as the rose form, is above 4.0 V (vs. Na/Na+), which is relatively high compared to that of other cathode materials. Thus, it can be employed as a potential high-voltage cathode material in Na-ion batteries. However, it is difficult to synthesize a pure rose phase because of its low phase stability, thus limiting its use in high-voltage applications. Herein, compositional-engineered, rose-phase Na2-2xCo1+xP2O7/C (x = 0, 0.1 and 0.2) nanopowder are prepared using a wet-chemical method. The Na2-2xCo1+xP2O7/C cathode shows high electrochemical reactivity with Na ions at 4.0 V, delivering high capacity and high energy density.

  19. Optimization of NaOH Molarity, LUSI Mud/Alkaline Activator, and Na2SiO3/NaOH Ratio to Produce Lightweight Aggregate-Based Geopolymer

    Directory of Open Access Journals (Sweden)

    Rafiza Abdul Razak

    2015-05-01

    Full Text Available This paper presents the mechanical function and characterization of an artificial lightweight geopolymer aggregate (ALGA using LUSI (Sidoarjo mud and alkaline activator as source materials. LUSI stands for LU-Lumpur and SI-Sidoarjo, meaning mud from Sidoarjo which erupted near the Banjarpanji-1 exploration well in Sidoarjo, East Java, Indonesia on 27 May 2006. The effect of NaOH molarity, LUSI mud/Alkaline activator (LM/AA ratio, and Na2SiO3/NaOH ratio to the ALGA are investigated at a sintering temperature of 950 °C. The results show that the optimum NaOH molarity found in this study is 12 M due to the highest strength (lowest AIV value of 15.79% with lower water absorption and specific gravity. The optimum LUSI mud/Alkaline activator (LM/AA ratio of 1.7 and the Na2SiO3/NaOH ratio of 0.4 gives the highest strength with AIV value of 15.42% with specific gravity of 1.10 g/cm3 and water absorption of 4.7%. The major synthesized crystalline phases were identified as sodalite, quartz and albite. Scanning Electron Microscope (SEM image showed more complete geopolymer matrix which contributes to highest strength of ALGA produced.

  20. Optimization of NaOH Molarity, LUSI Mud/Alkaline Activator, and Na2SiO3/NaOH Ratio to Produce Lightweight Aggregate-Based Geopolymer

    Science.gov (United States)

    Abdul Razak, Rafiza; Abdullah, Mohd Mustafa Al Bakri; Hussin, Kamarudin; Ismail, Khairul Nizar; Hardjito, Djwantoro; Yahya, Zarina

    2015-01-01

    This paper presents the mechanical function and characterization of an artificial lightweight geopolymer aggregate (ALGA) using LUSI (Sidoarjo mud) and alkaline activator as source materials. LUSI stands for LU-Lumpur and SI-Sidoarjo, meaning mud from Sidoarjo which erupted near the Banjarpanji-1 exploration well in Sidoarjo, East Java, Indonesia on 27 May 2006. The effect of NaOH molarity, LUSI mud/Alkaline activator (LM/AA) ratio, and Na2SiO3/NaOH ratio to the ALGA are investigated at a sintering temperature of 950 °C. The results show that the optimum NaOH molarity found in this study is 12 M due to the highest strength (lowest AIV value) of 15.79% with lower water absorption and specific gravity. The optimum LUSI mud/Alkaline activator (LM/AA) ratio of 1.7 and the Na2SiO3/NaOH ratio of 0.4 gives the highest strength with AIV value of 15.42% with specific gravity of 1.10 g/cm3 and water absorption of 4.7%. The major synthesized crystalline phases were identified as sodalite, quartz and albite. Scanning Electron Microscope (SEM) image showed more complete geopolymer matrix which contributes to highest strength of ALGA produced. PMID:26006238

  1. UTJECAJ POZITIVNE DISKRIMINACIJE NA UKLJUČIVANJE ŽENA NA TRŽIŠTE RADA U REPUBLICI HRVATSKOJ

    OpenAIRE

    Dovranić, Dora; Katavić, Ivica

    2016-01-01

    U početku 21. stoljeća često se koristi pojam pozitivne (afirmativne) diskriminacije. Pozitivna diskriminacija mjera je koju poduzima vlada, neka organizacija ili korporacija s ciljem da se smanje nejednakosti u društvu nastale upravo diskriminacijom, na način da se pružaju određene povlastice onima koji su pretrpjeli neku vrstu diskriminacije. Nastala je u Sjedinjenim Američkim Državama na inicijativu predsjednika Kennedyja, Johnsona i Nixona. Diskriminacija, nažalost, ima mnogo oblika, a ne...

  2. 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.

  3. 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)

  4. Reaction of metal oxides with molten mixtures NaPO3+NaCl

    International Nuclear Information System (INIS)

    Kovarskaya, E.N.; Mityakhina, V.S.; Rodionov, Yu.I.; Silin, M.Yu.

    1988-01-01

    By methods of solubility determination and paper chromatography it is shown, that Fe 2 O 3 solution in NaPO 3 +NaCl melts in the air relizes due to its chemical interaction with solvent resulting in formation of iron and sodium binary di- and monophosphates depending on melt-solvent initial composition, its attainment of equilibrium state and experiment temperature. It is established, that oxides increased solubility in melts with NaCl initial content ∼30 mol.% is specified by sodium tri- and tricyclophosphates presence in the melts. On this basis of NGR-spectroscopy data the presence of iron, europium, tin and sodium binary di- and monophosphates in some chloride-polyphosphate melts is confirmed

  5. Crystal structure of polyphosphates NaCd(PO3)3 and NaMn(PO3)3

    International Nuclear Information System (INIS)

    Murashova, E.V.; Chudinova, N.N.

    1997-01-01

    Crystal structure of NaCd(PO 3 ) 3 (1) and NaMn(PO 3 ) 3 (2) isostructural polyphosphates was determined for twin samples. Rhombic lattice parameters of (1): a = 14.678, b = 14.669, c = 14.705 A, sp. gr. P2 1 2 1 2 1 , Z = 16. The structure of compounds is of frame type. Polyphosphate chain with repetition period of 24 PO 4 tetrahedrons contacts with NaO 6 and M 2 O 6 octahedrons by means of common oxygen vertices. Similarities and differences in structure of mentioned polyphosphates and earlier analyzed NaMg(PO 3 ) 3 polyphosphate are noted [ru

  6. Effect of growth in lithium on ouabain binding, Na-K-ATPase and Na and K transport in hela cells.

    Science.gov (United States)

    Boardman, L J; Hume, S P; Lamb, J F; Polson, J

    1975-01-01

    1. HeLa cells were grown for 24 hr in growth medium in which part of the Na was replaced with Li. Ion contents, cell volumes and numbers, Na-K-ATPase and specific ouabain binding were measured. In some experiments the Na efflux and net Na transport was also measured. 2. Growth in Li caused a rise in the specific ouabain binding and membrane Na-K-ATPase of these cells. The Li concentrations in the cells necessary to produce this effect ranged up to 50 mM. 3. It is suggested that Li, like Na, acts on the genetic material of the cells to cause the production of more Na pumps within the membrane. PMID:124350

  7. Effects of EDTA-Na (Na ethylenediaminetetraacetate) upon the metabolism of radiostrontium and radioyttrium in mice

    Energy Technology Data Exchange (ETDEWEB)

    Kikuchi, T; Wakisaka, G; Kono, T; Hiroaki, A; Yamamasu, T; Sugawa, I

    1954-01-01

    The toxicity of EDTA-Na, inert Sr (NO/sub 3/)/sub 2/ and Ba (NO/sub 3/)/sub 2/ has been examined. Simultaneous injection of EDTA-Na showed no significant effect upon the distribution of radio-Sr in the bones of mice. The distribution of radio-Y in the bones of mice tended to decrease following the simultaneous subcutaneous injection of /sup 91/Y and EDTA-Na.

  8. Novel aspects of Na+,K+-ATPase

    OpenAIRE

    Aizman, Oleg

    2002-01-01

    Na,K-ATPase, an integral membrane protein expressed in each eukaryotic cell, serves as the major determinant of intracellular ion composition. In the current study we investigated novel aspects of Na,K-ATPase function and regulation. It is well established that Na,K-ATPase activity is regulated by reversible phosphorylation. New findings in this study are: 1) the level of intracellular Ca 2. concentration determines the functional effects of PKA and PKC-mediated Na,K-ATP...

  9. High-Performance Na-O2 Batteries Enabled by Oriented NaO2 Nanowires as Discharge Products.

    Science.gov (United States)

    Khajehbashi, S Mohammad B; Xu, Lin; Zhang, Guobin; Tan, Shuangshuang; Zhao, Yan; Wang, Lai-Sen; Li, Jiantao; Luo, Wen; Peng, Dong-Liang; Mai, Liqiang

    2018-06-13

    Na-O 2 batteries are emerging rechargeable batteries due to their high theoretical energy density and abundant resources, but they suffer from sluggish kinetics due to the formation of large-size discharge products with cubic or irregular particle shapes. Here, we report the unique growth of discharge products of NaO 2 nanowires inside Na-O 2 batteries that significantly boosts the performance of Na-O 2 batteries. For this purpose, a high-spin Co 3 O 4 electrocatalyst was synthesized via the high-temperature oxidation of pure cobalt nanoparticles in an external magnetic field. The discharge products of NaO 2 nanowires are 10-20 nm in diameter and ∼10 μm in length, characteristics that provide facile pathways for electron and ion transfer. With these nanowires, Na-O 2 batteries have surpassed 400 cycles with a fixed capacity of 1000 mA h g -1 , an ultra-low over-potential of ∼60 mV during charging, and near-zero over-potential during discharging. This strategy not only provides a unique way to control the morphology of discharge products to achieve high-performance Na-O 2 batteries but also opens up the opportunity to explore growing nanowires in novel conditions.

  10. Insight to the Thermal Decomposition and Hydrogen Desorption Behaviors of NaNH2-NaBH4 Hydrogen Storage Composite.

    Science.gov (United States)

    Pei, Ziwei; Bai, Ying; Wang, Yue; Wu, Feng; Wu, Chuan

    2017-09-20

    The lightweight compound material NaNH 2 -NaBH 4 is regarded as a promising hydrogen storage composite due to the high hydrogen density. Mechanical ball milling was employed to synthesize the composite NaNH 2 -NaBH 4 (2/1 molar ratio), and the samples were investigated utilizing thermogravimetric-differential thermal analysis-mass spectroscopy (TG-DTA-MS), X-ray diffraction (XRD), and Fourier transform infrared spectroscopy (FTIR) analyses. The full-spectrum test (range of the ratio of mass to charge: 0-200) shows that the released gaseous species contain H 2 , NH 3 , B 2 H 6 , and N 2 in the heating process from room temperature to 400 °C, and possibly the impurity gas B 6 H 12 also exists. The TG/DTA analyses show that the composite NaNH 2 -NaBH 4 (2/1 molar ratio) is conductive to generate hydrogen so that the dehydrogenation process can be finished before 400 °C. Moreover, the thermal decomposition process from 200 to 400 °C involves two-step dehydrogenation reactions: (1) Na 3 (NH 2 ) 2 BH 4 hydride decomposes into Na 3 BN 2 and H 2 (200-350 °C); (2) remaining Na 3 (NH 2 ) 2 BH 4 reacts with NaBH 4 and Na 3 BN 2 , generating Na, BN, NH 3 , N 2 , and H 2 (350-400 °C). The better mechanism understanding of the thermal decomposition pathway lays a foundation for tailoring the hydrogen storage performance of the composite complex hydrides system.

  11. Distinct pH dependencies of Na+/K+ selectivity at the two faces of Na,K-ATPase.

    Science.gov (United States)

    Cornelius, Flemming; Tsunekawa, Naoki; Toyoshima, Chikashi

    2018-02-09

    The sodium pump (Na,K-ATPase) in animal cells is vital for actively maintaining ATP hydrolysis-powered Na + and K + electrochemical gradients across the cell membrane. These ion gradients drive co- and countertransport and are critical for establishing the membrane potential. It has been an enigma how Na,K-ATPase discriminates between Na + and K + , despite the pumped ion on each side being at a lower concentration than the other ion. Recent crystal structures of analogs of the intermediate conformations E2·Pi·2K + and Na + -bound E1∼P·ADP suggest that the dimensions of the respective binding sites in Na,K-ATPase are crucial in determining its selectivity. Here, we found that the selectivity at each membrane face is pH-dependent and that this dependence is unique for each face. Most notable was a strong increase in the specific affinity for K + at the extracellular face ( i.e. E2 conformation) as the pH is lowered from 7.5 to 5. We also observed a smaller increase in affinity for K + on the cytoplasmic side (E1 conformation), which reduced the selectivity for Na + Theoretical analysis of the p K a values of ion-coordinating acidic amino acid residues suggested that the face-specific pH dependences and Na + /K + selectivities may arise from the protonation or ionization of key residues. The increase in K + selectivity at low pH on the cytoplasmic face, for instance, appeared to be associated with Asp 808 protonation. We conclude that changes in the ionization state of coordinating residues in Na,K-ATPase could contribute to altering face-specific ion selectivity. © 2018 by The American Society for Biochemistry and Molecular Biology, Inc.

  12. OGLAŠEVANJE NA FACEBOOKU

    OpenAIRE

    Renko, Katica

    2013-01-01

    V magistrskem delu smo se seznanili z oglaševanjem na Facebooku. S pregledom gradiva, ki nam je ponujeno, smo preverili pogoje, načine, oblike … oglaševanja, ki pa smo jih s pregledom situacije v praksi preverili in dopolnili. Ob zaključku dela lahko rečemo, da je oglaševanje preko FB enostavnejše, cenejše, dostopnejše, omogoča nam ažurnost in samo komunikacijo z naslovniki, ki so potencialni kupci naših ponudb. Množični mediji nam omogočajo mnogotero obliko oglaševanja. Izbrana oblika ponuja...

  13. Laser-induced ionization of Na vapor

    International Nuclear Information System (INIS)

    Wu, R.C.Y.; Judge, D.L.; Roussel, F.; Carre, B.; Breger, P.; Spiess, G.

    1982-01-01

    The production of Na 2 + ions by off-resonant laser excitation in the 5800-6200A region mainly results from two-photon absorption by the Na 2 molecule to highly excited gerade states followed by (a) direct ionization by absorbing a third photon or (b) coupling to the molecular Na 2 D 1 PIμ Rydberg state which is subsequently ionized by absorbing a third photon. This mechanism, i.e., a two-photon resonance three photon ionization process, explains a recent experimental observation of Roussel et al. It is suggested that the very same mechanism is also responsible for a similar observation reported by Polak-Dingels et al in their work using two crossed Na beams. In the latter two studies the laser-induced associative ionization processes were reported to be responsible for producing the Na 2 + ion. From the ratio of molecular to atomic concentration in the crossed beam experiment of Polak-Dingels et al we estimate that the cross section for producing Na 2 + through laser-induced associative ionization is at least four orders of magnitude smaller than ionization through the two-photon resonance three photon ionization process in Na 2 molecules

  14. Characterization and antibacterial activity of silver exchanged regenerated NaY zeolite from surfactant-modified NaY zeolite

    Energy Technology Data Exchange (ETDEWEB)

    Salim, Mashitah Mad; Malek, Nik Ahmad Nizam Nik, E-mail: niknizam@fbb.utm.my

    2016-02-01

    The antibacterial activity of regenerated NaY zeolite (thermal treatment from cetyltrimethyl ammonium bromide (CTAB)-modified NaY zeolite and pretreatment with Na ions) loaded with silver ions were examined using the broth dilution minimum inhibitory concentration (MIC) method against Escherichia coli (E. coli ATCC 11229) and Staphylococcus aureus (S. aureus ATCC 6538). X-ray diffraction (XRD), attenuated total reflectance–Fourier transform infrared (ATR–FTIR) spectroscopy, field emission scanning electron microscopy (FESEM), energy dispersive X-ray (EDX) and chemical elemental analyses were used to characterize the regenerated NaY and AgY zeolites. The XRD patterns indicated that the calcination and addition of silver ions on regenerated NaY zeolite did not affect the structure of the regenerated NaY zeolite as the characteristic peaks of the NaY zeolite were retained, and no new peaks were observed. The regenerated AgY zeolite showed good antibacterial activity against both bacteria strains in distilled water, and the antibacterial activity of the samples increased with increasing Ag loaded on the regenerated AgY zeolite; the regenerated AgY zeolite was more effective against E. coli than S. aureus. However, the antibacterial activity of the regenerated AgY was not effective in saline solution for both bacteria. The study showed that CTAB-modified NaY zeolite materials could be regenerated to NaY zeolite using thermal treatment (550 °C, 5 h) and this material has excellent performance as an antibacterial agent after silver ions loading. - Highlights: • Thermal treatment was used to regenerate surfactant modified zeolite. • The regenerated NaY zeolite formed was added with different silver loadings. • Regenerated AgY zeolite was tested for antibacterial activity on E. coli and S. aureus. • The antibacterial activity increased with increased of the amount of silver loadings. • The zeolite structure did not change with thermal and modification

  15. Characterization and antibacterial activity of silver exchanged regenerated NaY zeolite from surfactant-modified NaY zeolite

    International Nuclear Information System (INIS)

    Salim, Mashitah Mad; Malek, Nik Ahmad Nizam Nik

    2016-01-01

    The antibacterial activity of regenerated NaY zeolite (thermal treatment from cetyltrimethyl ammonium bromide (CTAB)-modified NaY zeolite and pretreatment with Na ions) loaded with silver ions were examined using the broth dilution minimum inhibitory concentration (MIC) method against Escherichia coli (E. coli ATCC 11229) and Staphylococcus aureus (S. aureus ATCC 6538). X-ray diffraction (XRD), attenuated total reflectance–Fourier transform infrared (ATR–FTIR) spectroscopy, field emission scanning electron microscopy (FESEM), energy dispersive X-ray (EDX) and chemical elemental analyses were used to characterize the regenerated NaY and AgY zeolites. The XRD patterns indicated that the calcination and addition of silver ions on regenerated NaY zeolite did not affect the structure of the regenerated NaY zeolite as the characteristic peaks of the NaY zeolite were retained, and no new peaks were observed. The regenerated AgY zeolite showed good antibacterial activity against both bacteria strains in distilled water, and the antibacterial activity of the samples increased with increasing Ag loaded on the regenerated AgY zeolite; the regenerated AgY zeolite was more effective against E. coli than S. aureus. However, the antibacterial activity of the regenerated AgY was not effective in saline solution for both bacteria. The study showed that CTAB-modified NaY zeolite materials could be regenerated to NaY zeolite using thermal treatment (550 °C, 5 h) and this material has excellent performance as an antibacterial agent after silver ions loading. - Highlights: • Thermal treatment was used to regenerate surfactant modified zeolite. • The regenerated NaY zeolite formed was added with different silver loadings. • Regenerated AgY zeolite was tested for antibacterial activity on E. coli and S. aureus. • The antibacterial activity increased with increased of the amount of silver loadings. • The zeolite structure did not change with thermal and modification

  16. Carbon dioxide sequestration using NaHSO4 and NaOH: A dissolution and carbonation optimisation study.

    Science.gov (United States)

    Sanna, Aimaro; Steel, Luc; Maroto-Valer, M Mercedes

    2017-03-15

    The use of NaHSO 4 to leach out Mg fromlizardite-rich serpentinite (in form of MgSO 4 ) and the carbonation of CO 2 (captured in form of Na 2 CO 3 using NaOH) to form MgCO 3 and Na 2 SO 4 was investigated. Unlike ammonium sulphate, sodium sulphate can be separated via precipitation during the recycling step avoiding energy intensive evaporation process required in NH 4 -based processes. To determine the effectiveness of the NaHSO 4 /NaOH process when applied to lizardite, the optimisation of the dissolution and carbonation steps were performed using a UK lizardite-rich serpentine. Temperature, solid/liquid ratio, particle size, concentration and molar ratio were evaluated. An optimal dissolution efficiency of 69.6% was achieved over 3 h at 100 °C using 1.4 M sodium bisulphate and 50 g/l serpentine with particle size 75-150 μm. An optimal carbonation efficiency of 95.4% was achieved over 30 min at 90 °C and 1:1 magnesium:sodium carbonate molar ratio using non-synthesised solution. The CO 2 sequestration capacity was 223.6 g carbon dioxide/kg serpentine (66.4% in terms of Mg bonded to hydromagnesite), which is comparable with those obtained using ammonium based processes. Therefore, lizardite-rich serpentinites represent a valuable resource for the NaHSO 4 /NaOH based pH swing mineralisation process. Copyright © 2016 Elsevier Ltd. All rights reserved.

  17. Characterization and antibacterial activity of silver exchanged regenerated NaY zeolite from surfactant-modified NaY zeolite.

    Science.gov (United States)

    Salim, Mashitah Mad; Malek, Nik Ahmad Nizam Nik

    2016-02-01

    The antibacterial activity of regenerated NaY zeolite (thermal treatment from cetyltrimethyl ammonium bromide (CTAB)-modified NaY zeolite and pretreatment with Na ions) loaded with silver ions were examined using the broth dilution minimum inhibitory concentration (MIC) method against Escherichia coli (E. coli ATCC 11229) and Staphylococcus aureus (S. aureus ATCC 6538). X-ray diffraction (XRD), attenuated total reflectance-Fourier transform infrared (ATR-FTIR) spectroscopy, field emission scanning electron microscopy (FESEM), energy dispersive X-ray (EDX) and chemical elemental analyses were used to characterize the regenerated NaY and AgY zeolites. The XRD patterns indicated that the calcination and addition of silver ions on regenerated NaY zeolite did not affect the structure of the regenerated NaY zeolite as the characteristic peaks of the NaY zeolite were retained, and no new peaks were observed. The regenerated AgY zeolite showed good antibacterial activity against both bacteria strains in distilled water, and the antibacterial activity of the samples increased with increasing Ag loaded on the regenerated AgY zeolite; the regenerated AgY zeolite was more effective against E. coli than S. aureus. However, the antibacterial activity of the regenerated AgY was not effective in saline solution for both bacteria. The study showed that CTAB-modified NaY zeolite materials could be regenerated to NaY zeolite using thermal treatment (550°C, 5h) and this material has excellent performance as an antibacterial agent after silver ions loading. Copyright © 2015 Elsevier B.V. All rights reserved.

  18. Composition and thermochemistry of the equilibrium vapour of the systems NaI-FeI2 and NaI-PbI2

    International Nuclear Information System (INIS)

    Hilpert, K.; Gerads, H.; Koberts, D.; Miller, M.

    1987-01-01

    The vaporization of NaI/FeI 2 and NaI/PbI 2 samples of equimolar composition was investigated was investigated in the temperature ranges between 574 to 683 K and 562 to 669 K, respectively, by using the mass spectrometric Knudsen effusion method. The gaseous species I, I 2 , NaI, (NaI) 2 , FeI 2 , (FeI 2 ) 2 , FeI 3 , NaFeI 3 , and Na 2 FeI 4 (NaI-FeI 2 system) as well as NaI, (NaI) 2 , PbI 2 , (PbI 2 ) 2 , and NaPbI 3 (NaI-PbI 2 system) are present in the equilibrium vapours. The equilibrium partial pressures of these species were determined with the exception of I, I 2 , and FeI 3 . Enthalpies and entropies of dissociation resulted for the reactions NaFeI 3 (g) ↔ NaI(g)+FeI 2 (g) (1), Na 2 FeI 4 (g) ↔ 2NaI(g)+FeI 2 (g) and (2) NaPbI 3 (g) ↔ NaI(g)+PbI 2 (g) (3) as Δ d H 298 0 (Eq. (1)) = 184±5 kJ mol -1 , Δ d S 298 0 (Eq. (1)) = 143±8 J mol -1 K -1 ; Δ d H 298 0 (Eq. (2)) = 333±9 kJ mol -1 , Δ d S 298 0 (Eq. (2)) = 274±14 J mol -1 K -1 ; and Δ d H 298 0 (Eq. (3)) = 168±5 kJ mol -1 , Δ d S 298 0 (Eq. (3)) = 151±9 J mol -1 K -1 . Equilibrium constants for these reactions are additionally given. The pressures of NaFeI 3 (g) and NaPbI 3 (g) as all as their enthalpies of dissociation are discussed with respect to their significance of semi empirical rules. (orig.)

  19. Adsorption and Formation of Small Na Clusters on Pristine and Double-Vacancy Graphene for Anodes of Na-Ion Batteries.

    Science.gov (United States)

    Liang, Zhicong; Fan, Xiaofeng; Zheng, Weitao; Singh, David J

    2017-05-24

    Layered carbon is a likely anode material for Na-ion batteries (NIBs). Graphitic carbon has a low capacity of approximately 35 (mA h)/g due to the formation of NaC 64 . Using first-principles methods including van der Waals interactions, we analyze the adsorption of Na ions and clusters on graphene in the context of anodes. The interaction between Na ions and graphene is found to be weak. Small Na clusters are not stable on the surface of pristine graphene in the electrochemical environment of NIBs. However, we find that Na ions and clusters can be stored effectively on defected graphene that has double vacancies. In addition, the adsorption energy of small Na clusters near a double vacancy is found to decrease with increasing cluster size. With high concentrations of vacancies the capacity of Na on defective graphene is found to be as much as 10-30 times higher than that of graphitic carbon.

  20. 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.

  1. Novel regulation of cardiac Na pump via phospholemman.

    Science.gov (United States)

    Pavlovic, Davor; Fuller, William; Shattock, Michael J

    2013-08-01

    As the only quantitatively significant Na efflux pathway from cardiac cells, the Na/K ATPase (Na pump) is the primary regulator of intracellular Na. The transmembrane Na gradient it establishes is essential for normal electrical excitability, numerous coupled-transport processes and, as the driving force for Na/Ca exchange, thus setting cardiac Ca load and contractility. As Na influx varies with electrical excitation, heart rate and pathology, the dynamic regulation of Na efflux is essential. It is now widely recognized that phospholemman, a 72 amino acid accessory protein which forms part of the Na pump complex, is the key nexus linking cellular signaling to pump regulation. Phospholemman is the target of a variety of post-translational modifications (including phosphorylation, palmitoylation and glutathionation) and these can dynamically alter the activity of the Na pump. This review summarizes our current understanding of the multiple regulatory mechanisms that converge on phospholemman and govern NA pump activity in the heart. The corrected Fig. 4 is reproduced below. The publisher would like to apologize for any inconvenience caused. [corrected]. Copyright © 2013. Published by Elsevier Ltd.

  2. All new for NA62

    CERN Multimedia

    Antonella Del Rosso

    2012-01-01

    This week sees the start of the first run of the new NA62 experiment. This will be a unique opportunity for the collaboration to test its new beam, new detectors and new data acquisition system before the physics run in 2014. Speaking to the Bulletin, the NA62 technical coordinator Ferdinand Hahn shares the many challenges that the various teams faced to be on time for beam. Ready, steady, start!   A Large Angle Veto detector (white) in place in the NA62 decay volume (blue). With components from almost all the detectors in place downstream of the decay point of the mother particles – the kaons – and of the KTAG detector that tags the kaons before they decay, NA62 is ready for its first technical run. This unique run will test all the equipment as well as the trigger and the data acquisition systems. “This year, we will have about five weeks of beam from the SPS before the long shutdown of all the CERN machines,” says Ferdinand Hahn, NA62 Technical Co-...

  3. Effect of chloride substitution on the order–disorder transition in NaBH4 and Na11BD4

    International Nuclear Information System (INIS)

    Olsen, Jørn Eirik; Karen, Pavel; Sørby, Magnus H.; Hauback, Bjørn C.

    2014-01-01

    Graphical abstract: Interactions that order the BD 4 - tetrahedra below the order–disorder transition became increasingly frustrated by the solute in the Na( 11 BD 4 ) 1−x Cl x solid solutions, and the order disappears at x = 0.158. Highlights: • The order–disorder transition temperature for Na(BH 4 ) 1−x Cl x and Na( 11 BD 4 ) 1−x Cl x is highly dependent on the Cl-content, x. • The transition is characterized by DSC for Na( 11 BD 4 ) 1−x Cl x for x = 0, 0.10 and 0.15. • No transition is observed for x ⩾ 0.20 on cooling to 8 K. • The crystal structures are reported for Na 11 BD 4 at room temperature and 8 K and Na( 11 BD 4 ) 1−x Cl x (x = 0.10, 0.15, 0.20 and 0.25) at 8 K from powder neutron diffraction. -- Abstract: Phase transition associated with anion disordering over two orientations in Na 11 BD 4 (NaBH 4 ) and its solid solutions with NaCl, Na( 11 BD 4 ) 1−x Cl x , is investigated with powder diffraction (neutron and synchrotron radiation), differential scanning calorimetry and Raman spectroscopy. Upon heating, the transition temperature extrapolated to zero rate of heating is 192.2 K for Na 11 BD 4 , ΔS = 4.41 J/mol K, hysteresis 1.7 K and the volume increase 0.43%. Thermal parameters of the transition in Na( 11 BD 4 ) 1−x Cl x follow a colligative-property model of an ideal solution, with x = 0.158(1) as the critical concentration at which the ordering interactions and the transition itself are eliminated. On approaching this limit, the tetragonal distortion of the ordered structure decreases somewhat towards the cubic average, and this is associated with a partial disorder of the tetrahedral anions seen by diffraction methods. In fact, a 3% disorder is already present in the pure solvent of the solid solution (Na 11 BD 4 ) at 8 K

  4. Neutron diffraction studies of the Na-ion battery electrode materials NaCoCr{sub 2}(PO{sub 4}){sub 3}, NaNiCr{sub 2}(PO{sub 4}){sub 3}, and Na{sub 2}Ni{sub 2}Cr(PO{sub 4}){sub 3}

    Energy Technology Data Exchange (ETDEWEB)

    Yahia, H. Ben [Qatar Environment and Energy Research Institute, Hamad Bin Khalifa University, Qatar Foundation, P.O. Box 5825 Doha (Qatar); Essehli, R., E-mail: ressehli@qf.org.qa [Qatar Environment and Energy Research Institute, Hamad Bin Khalifa University, Qatar Foundation, P.O. Box 5825 Doha (Qatar); Avdeev, M. [Australian Nuclear Science and Technology Organisation, New Illawarra Road, Lucas Heights NSW 2234 (Australia); Park, J-B.; Sun, Y-K. [Department of Energy Engineering Hanyang University, 17 Haengdang-dong, Seongdong-gu, Seoul 133-791 (Korea, Republic of); Al-Maadeed, M.A. [Center for Advanced Materials (CAM), Qatar University, 2713 Doha (Qatar); Belharouak, I., E-mail: ibelharouak@qf.org.qa [Qatar Environment and Energy Research Institute, Hamad Bin Khalifa University, Qatar Foundation, P.O. Box 5825 Doha (Qatar)

    2016-06-15

    The new compounds NaCoCr{sub 2}(PO{sub 4}){sub 3}, NaNiCr{sub 2}(PO{sub 4}){sub 3}, and Na{sub 2}Ni{sub 2}Cr(PO{sub 4}){sub 3} were synthesized by sol-gel method and their crystal structures were determined by using neutron powder diffraction data. These compounds were characterized by galvanometric cycling and cyclic voltammetry. NaCoCr{sub 2}(PO{sub 4}){sub 3}, NaNiCr{sub 2}(PO{sub 4}){sub 3}, and Na{sub 2}Ni{sub 2}Cr(PO{sub 4}){sub 3} crystallize with a stuffed α-CrPO{sub 4}-type structure. The structure consists of a 3D-framework made of octahedra and tetrahedra that are sharing corners and/or edges generating channels along [100] and [010], in which the sodium atoms are located. Of significance, in the structures of NaNiCr{sub 2}(PO{sub 4}){sub 3}, and Na{sub 2}Ni{sub 2}Cr(PO{sub 4}){sub 3} a statistical disorder Ni{sup 2+}/Cr{sup 3+} was observed on both the 8g and 4a atomic positions, whereas in NaCoCr{sub 2}(PO{sub 4}){sub 3} the statistical disorder Co{sup 2+}/Cr{sup 3+} was only observed on the 8g atomic position. When tested as negative electrode materials, NaCoCr{sub 2}(PO{sub 4}){sub 3}, NaNiCr{sub 2}(PO{sub 4}){sub 3}, and Na{sub 2}Ni{sub 2}Cr(PO{sub 4}){sub 3} delivered specific capacities of 352, 385, and 368 mA h g{sup −1}, respectively, which attests to the electrochemical activity of sodium in these compounds. - Highlights: • NaCoCr{sub 2}(PO{sub 4}){sub 3}, NaNiCr{sub 2}(PO{sub 4}){sub 3}, and Na{sub 2}Ni{sub 2}Cr(PO{sub 4}){sub 3} were synthesized by sol-gel method. • The crystal structures were determined by using neutron powder diffraction data. • The three compounds crystallize with a stuffed α-CrPO{sub 4}-type structure. • The three compounds were tested as anodes in sodium-ion batteries. • Relatively high specific capacities were obtained for these compounds.

  5. Evaluation of NaX and NaY packed beds for chromium uptake from multicomponent solution

    Directory of Open Access Journals (Sweden)

    Maria Angélica Simões Dornellas de Barros

    2014-04-01

    Full Text Available In this paper the removal of chromium from Cr/Ca/Mg/K and Cr/Ca/Mg/K/Na solutions was investigated in NaX and NaY packed beds. The breakthrough curves presented some overshooting phenomena where chromium ions displaced the previous exchanged cations. Length of unused bed, overall mass transfer coefficient, operational ratio and dimensionless variance were obtained. According to such mass transfer parameters it was concluded that the chromium uptake is influenced by the competition and interaction of the entering ions. Such influences were verified through some differences in the dynamic selectivity obtained for each system. NaY seemed to have a higher affinity towards Cr3+ and its sites were more efficiently used in the ion exchange process.

  6. Water transport by the renal Na(+)-dicarboxylate cotransporter

    DEFF Research Database (Denmark)

    Meinild, A K; Loo, D D; Pajor, A M

    2000-01-01

    . This solute-coupled influx of water took place in the absence of, and even against, osmotic gradients. There was a strict stoichiometric relationship between Na(+), substrate, and water transport of 3 Na(+), 1 dicarboxylate, and 176 water molecules/transport cycle. These results indicate that the renal Na......This study investigated the ability of the renal Na(+)-dicarboxylate cotransporter, NaDC-1, to transport water. Rabbit NaDC-1 was expressed in Xenopus laevis oocytes, cotransporter activity was measured as the inward current generated by substrate (citrate or succinate), and water transport...... was monitored by the changes in oocyte volume. In the absence of substrates, oocytes expressing NaDC-1 showed an increase in osmotic water permeability, which was directly correlated with the expression level of NaDC-1. When NaDC-1 was transporting substrates, there was a concomitant increase in oocyte volume...

  7. Pioneering instrumentation aspects of NA60

    International Nuclear Information System (INIS)

    David, Andre

    2004-01-01

    NA60 is taking data with proton and heavy-ion beams at the CERN SPS. Although building up on previous experiments, the dimuon physics programme of NA60 places very demanding requirements on its new detectors, in terms of radiation tolerance, granularity and read-out electronics speed. We start by comparing dimuon detection strategies in NA60 with those of previous experiments. We then describe the new detectors used in NA60, placing particular emphasis on their technological pioneering aspects as well as on their contributions to the overall physics performance of the experiment

  8. Occlusion of 22Na+ and 86Rb+ in membrane-bound and soluble protomeric alpha beta-units of Na,K-ATPase

    International Nuclear Information System (INIS)

    Vilsen, B.; Andersen, J.P.; Petersen, J.; Jorgensen, P.L.

    1987-01-01

    In this work, we examined occlusion of 22 Na+ and 86 Rb+ in membranous and detergent-solubilized Na,K-ATPase from outer renal medulla. Optimum conditions for occlusion of 22 Na+ were provided by formation of the phosphorylated complex from the beta,gamma-bidentate complex of chromium (III) with ATP (CrATP). Release of occluded cations occurred at equally slow rates in soluble and membrane-bound Na,K-ATPase. Values of 22 Na+ occlusion as high as 11 nmol/mg of protein were measured, corresponding to 1.8-2.7 mol of Na+/mol of phosphorylated Na,K-ATPase as determined by 32 P incorporation from [gamma- 32 P]CrATP. Maximum capacity for phosphorylation from [gamma- 32 P]CrATP was 6 nmol/mg of protein and equal to capacities for binding of [48V]vanadate and [ 3 H]ouabain. The stoichiometry for occlusion of Rb+ was close to 2 Rb+ ions/phosphorylation site. In an analytical ultracentrifuge, the soluble Na+- or Rb+-occluded complexes showed sedimentation velocities (S20,w = 6.8-7.4) consistent with monomeric alpha beta-units. The data show that soluble monomeric alpha beta-units of Na,K-ATPase can occlude Rb+ or Na+ with the same stoichiometry as the membrane-bound enzyme. The structural basis for occlusion of cations in Na,K-ATPase is suggested to be the formation of a cavity inside a monomeric alpha beta-unit constituting the minimum protein unit required for active Na,K-transport

  9. Transcriptional regulators of Na, K-ATPase subunits

    Directory of Open Access Journals (Sweden)

    Zhiqin eLi

    2015-10-01

    Full Text Available The Na,K-ATPase classically serves as an ion pump creating an electrochemical gradient across the plasma membrane that is essential for transepithelial transport, nutrient uptake and membrane potential. In addition, Na,K-ATPase also functions as a receptor, a signal transducer and a cell adhesion molecule. With such diverse roles, it is understandable that the Na,K-ATPase subunits, the catalytic alpha-subunit, the beta-subunit and the FXYD proteins, are controlled extensively during development and to accommodate physiological needs. The spatial and temporal expression of Na,K-ATPase is partially regulated at the transcriptional level. Numerous transcription factors, hormones, growth factors, lipids and extracellular stimuli modulate the transcription of the Na,K-ATPase subunits. Moreover, epigenetic mechanisms also contribute to the regulation of Na,K-ATPase expression. With the ever growing knowledge about diseases associated with the malfunction of Na,K-ATPase, this review aims at summarizing the best-characterized transcription regulators that modulate Na,K-ATPase subunit levels. As abnormal expression of Na,K-ATPase subunits have been observed in many carcinoma, we will also discuss transcription factors that are associated with epithelial-to-mesenchymal transition, a crucial step in the progression of many tumors to malignant disease.

  10. Sepsis does not alter red blood cell glucose metabolism or Na+ concentration: A 2H-, 23Na-NMR study

    International Nuclear Information System (INIS)

    Hotchkiss, R.S.; Song, S.K.; Ling, C.S.; Ackerman, J.J.; Karl, I.E.

    1990-01-01

    The effects of sepsis on intracellular Na+ concentration ([Na+]i) and glucose metabolism were examined in rat red blood cells (RBCs) by using 23Na- and 2H-nuclear magnetic resonance (NMR) spectroscopy. Sepsis was induced in 15 halothane-anesthetized female Sprague-Dawley rats by using the cecal ligation and perforation technique; 14 control rats underwent cecal manipulation without ligation. The animals were fasted for 36 h, but allowed free access to water. At 36 h postsurgery, RBCs were examined by 23Na-NMR by using dysprosium tripolyphosphate as a chemical shift reagent. Human RBCs from 17 critically ill nonseptic patients and from 7 patients who were diagnosed as septic were also examined for [Na+]i. Five rat RBC specimens had [Na+]i determined by both 23Na-NMR and inductively coupled plasma-atomic emission spectroscopy (ICP-AES). For glucose metabolism studies, RBCs from septic and control rats were suspended in modified Krebs-Henseleit buffer containing [6,6-2H2]glucose and examined by 2H-NMR. No significant differences in [Na+]i or glucose utilization were found in RBCs from control or septic rats. There were no differences in [Na+]i in the two groups of patients. The [Na+]i determined by NMR spectroscopy agreed closely with measurements using ICP-AES and establish that 100% of the [Na+]i of the RBC is visible by NMR. Glucose measurements determined by 2H-NMR correlated closely (correlation coefficient = 0.93) with enzymatic analysis. These studies showed no evidence that sepsis disturbed RBC membrane function or metabolism

  11. SPOLNO NADLEGOVANJE NA DELOVNEM MESTU

    OpenAIRE

    Rubič, Gašper

    2016-01-01

    V diplomskem delu smo v uvodu predstavili problem spolnega nadlegovanja na delovnem mestu in predstavili podjetje TEKSTIL d.d. V nadaljevanju smo z anketo raziskali, ali problem spolnega nadlegovanja na delovnem mestu v obravnavanem podjetju obstaja in če, kako se nanj odziva okolje. V teoretičnem delu smo nadaljevali in predstavili definicijo spolnega nadlegovanja, ki je kakršna koli oblika nezaželenega verbalnega in neverbalnega ali fizičnega ravnanja spolne narave z učinkom ali nameno...

  12. Photodesorption of Na atoms from rough Na surfaces

    DEFF Research Database (Denmark)

    Balzer, Frank; Gerlach, R.; Manson, J.R.

    1997-01-01

    We investigate the desorption of Na atoms from large Na clusters deposited on dielectric surfaces. High-resolution translational energy distributions of the desorbing atoms are determined by three independent methods, two-photon laser-induced fluorescence, as well as single-photon and resonance......-enhanced two-photon ionization techniques. Upon variation of surface temperature and for different substrates (mica vs lithium fluoride) clear non-Maxwellian time-of-flight distributions are observed with a cos θ angular dependence and most probable kinetic energies below that expected of atoms desorbing from...... atoms are scattered by surface vibrations. Recent experiments providing time constants for the decay of the optical excitations in the clusters support this model. The excellent agreement between experiment and theory indicates the importance of both absorption of the laser photons via direct excitation...

  13. Evaluation of {sup 23}Na(n,2n){sup 22}Na reaction cross-sections

    Energy Technology Data Exchange (ETDEWEB)

    Manokhin, V N [Institute of Physics and Power Engineering, Obninsk (Russian Federation)

    1997-06-01

    Using available experimental data and (n,2n) excitation function systematics {sup 23}Na(n,2n){sup 22}Na reaction cross-sections were evaluated for energies ranging from the reaction threshold to 20 MeV. (author). 21 refs, 1 fig., 2 tabs.

  14. Formation of hydroxyl groups and exchange with deuterium on NaHX and NaHY zeolites

    International Nuclear Information System (INIS)

    Kubelkova, L.; Novakova, J.

    1976-01-01

    Deammoniation and dehydroxylation of Na(NH 4 )X and Na(NH 4 )Y zeolites were compared. With the X type, both processes overlapped and proceeded more easily than with the Y type. Both H forms contained structural OH groups and hydroxyls denoted as SiOH, to which the 3740 cm -1 band in the IR spectrum was assigned. In addition, the NaHX zeolite contained OH groups characterized by the 3700 and 3600 cm -1 bands. Certain differences in the behaviour of NaHX and NaHY zeolites during deammoniation and dehydroxylation might be attributed to the presence of ''non-localizable'' H atoms. The active sites for the D 2 -OH exchange were probably formed during dehydroxylation. Hydrogen in SiOH groups was replaced by deuterium in both zeolite types more slowly than H atoms in other OH groups, which influenced the kinetic variations in the gaseous phase. The presence of water in the gaseous phase affected the kinetics and could distort the determination of the number of H atoms bound in the zeolites. (author)

  15. 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

  16. High resolution laser spectroscopy of the D lines of on-line produced 21Na, 22Na, 24Na, 25Na using a new high sensitivity method of detection of optical resonances

    International Nuclear Information System (INIS)

    Huber, G.; Thibault, G.; Klapisch, R.; Duong, H.T.; Vialle, J.L.; Pinard, I.; Juncar, P.; Jacquinot, P.

    1975-01-01

    A polyisotopic sodium beam of 21 - 25 Na, produced by spallation of Al, was illuminated by a tunable dye laser. The atomic beam, analyzed by a sixpole magnet is then ionized and detected after a mass spectrometer. The results are the isotope shifts, nuclear magnetic moment and quadrupole moment of 25 Na [fr

  17. OGLAŠEVANJE NA SOCIALNEM OMREŽJU FACEBOOK, NA PRIMERU SPLETICNA.SI

    OpenAIRE

    Reisman, Nina

    2011-01-01

    Internet je od svojega razvoja dolgo časa obstajal kot prostor za enostransko komunikacijo. Isto se je dogajalo na televiziji, radiu in časopisih, kjer je javnost sprejemala informacije, ki jih je nekdo pripravil. Tradicionalni mediji so hitro doumeli, da takšna vrsta komunikacije ni naravna in ne predstavlja najboljšega ohranjanja gledalcev in poslušalcev. Začela se je uporabljati dvosmerna komunikacija. Trenutno v svetu najbolje poznan primer dvosmerne komunikacije je socialno omrežje F...

  18. FTIR spectra of the solid solutions (Na0.88K0.12)VO3, (Na0.5K0.5)VO3, and Na(V0.66P0.34)O3

    Science.gov (United States)

    de Waal, D.; Heyns, A. M.

    1992-03-01

    It is known that three different solid solutions, (Na0.88K0.12)VO3, (Na0.5K0.5)VO3 and Na(V0.66P0.34)O3, form in the (Na,K)(V,P)O3 system. These compounds all have monoclinic crystal structures similar to the pure alkali metal metavanadates containing small cations, e.g. Li+ and Na+ (Space group C2/c). Metavanadates with large cations like K+, Rb+, C+s and NH+4 form orthorhombic crystals, space group Pbcm. All those are structurally related to the silicate pyroxenes. Na(V0.66P0.34)O3 and (Na0.88K0.12)VO3 have the same modified diopside structure as (alpha) - NaVO3 while (Na0.5K0.5)VO3 adopts the true diopside structure. The infrared spectra of the three solid solutions are reported here in comparison with those of (alpha) -NaVO3 and KVO3. The results are also correlated with those obtained in two independent high pressure Raman studies of NH4VO3 and RbVO3 as the introduction of a larger cation like K+ should increase the pressure in the structure.

  19. Medetomidīna un detomidīna hidrogēnhlorīdu struktūra noteikšana

    OpenAIRE

    Smuļko, Irina

    2012-01-01

    Medetomidīna un detomidīna hidrogēnhlorīdu struktūras noteikšana. Smuļko I., zinātniskais vadītājs Dr. ķīm., asoc. prof. Actiņš A. Maģistra darbs, 52 lappuses, 37 attēli, 6 tabulas, 29 literatūras avoti. Latviešu valodā. Maģistra darbā pētītas farmaceitiski aktīvās vielas – medetomidīna un detomidīna hidrogēnhlorīdi. Veikti mēģinājumi detomidīna bezūdens formas un monohidrāta struktūras noteikšanai, kā arī medetomidīna bezūdens formu A un B struktūras noteikšanai. Struktūras noteikšanai iz...

  20. NAKUPOVANJE NA SPLETU

    OpenAIRE

    Visenjak, Monika

    2013-01-01

    Nakupovanje na spletu je prihodnost poslovanja. Za podjetja pomeni manjše stroške, lažje prilagajanje tržnim pogojem. Hitreje lahko razvijajo odnose in analizirajo uporabnike, saj jim je dan dostop o nakupnih podatkih uporabnika. Za potrošnike je nakupovanje na spletu možnost hitrega, preprostega in učinkovitega nakupovanja od doma ali pisarne. Pomembno je, da se seznanijo z vsemi informacijami in pogoji spletnih trgovin, saj se lahko le tako izognejo nezadovoljstvu ob nakupu v spletni trgovi...

  1. The Na+ transporter, TaHKT1;5-D, limits shoot Na+ accumulation in bread wheat

    KAUST Repository

    Byrt, Caitlin Siobhan

    2014-10-01

    Bread wheat (Triticum aestivum L.) has a major salt tolerance locus, Kna1, responsible for the maintenance of a high cytosolic K+/Na+ ratio in the leaves of salt stressed plants. The Kna1 locus encompasses a large DNA fragment, the distal 14% of chromosome 4DL. Limited recombination has been observed at this locus making it difficult to map genetically and identify the causal gene. Here, we decipher the function of TaHKT1;5-D, a candidate gene underlying the Kna1 locus. Transport studies using the heterologous expression systems Saccharomyces cerevisiae and Xenopus laevis oocytes indicated that TaHKT1;5-D is a Na+-selective transporter. Transient expression in Arabidopsis thaliana mesophyll protoplasts and in situ polymerase chain reaction indicated that TaHKT1;5-D is localised on the plasma membrane in the wheat root stele. RNA interference-induced silencing decreased the expression of TaHKT1;5-D in transgenic bread wheat lines which led to an increase in the Na+ concentration in the leaves. This indicates that TaHKT1;5-D retrieves Na+ from the xylem vessels in the root and has an important role in restricting the transport of Na+ from the root to the leaves in bread wheat. Thus, TaHKT1;5-D confers the essential salinity tolerance mechanism in bread wheat associated with the Kna1 locus via shoot Na+ exclusion and is critical in maintaining a high K+/Na+ ratio in the leaves. These findings show there is potential to increase the salinity tolerance of bread wheat by manipulation of HKT1;5 genes.

  2. The Na+ transporter, TaHKT1;5-D, limits shoot Na+ accumulation in bread wheat

    KAUST Repository

    Byrt, Caitlin Siobhan; Xu, Bo; Krishnan, Mahima; Lightfoot, Damien; Athman, Asmini; Jacobs, Andrew Keith; Watson-Haigh, Nathan S.; Plett, Darren; Munns, Rana; Tester, Mark A.; Gilliham, Matthew

    2014-01-01

    Bread wheat (Triticum aestivum L.) has a major salt tolerance locus, Kna1, responsible for the maintenance of a high cytosolic K+/Na+ ratio in the leaves of salt stressed plants. The Kna1 locus encompasses a large DNA fragment, the distal 14% of chromosome 4DL. Limited recombination has been observed at this locus making it difficult to map genetically and identify the causal gene. Here, we decipher the function of TaHKT1;5-D, a candidate gene underlying the Kna1 locus. Transport studies using the heterologous expression systems Saccharomyces cerevisiae and Xenopus laevis oocytes indicated that TaHKT1;5-D is a Na+-selective transporter. Transient expression in Arabidopsis thaliana mesophyll protoplasts and in situ polymerase chain reaction indicated that TaHKT1;5-D is localised on the plasma membrane in the wheat root stele. RNA interference-induced silencing decreased the expression of TaHKT1;5-D in transgenic bread wheat lines which led to an increase in the Na+ concentration in the leaves. This indicates that TaHKT1;5-D retrieves Na+ from the xylem vessels in the root and has an important role in restricting the transport of Na+ from the root to the leaves in bread wheat. Thus, TaHKT1;5-D confers the essential salinity tolerance mechanism in bread wheat associated with the Kna1 locus via shoot Na+ exclusion and is critical in maintaining a high K+/Na+ ratio in the leaves. These findings show there is potential to increase the salinity tolerance of bread wheat by manipulation of HKT1;5 genes.

  3. Osmotic and ionic effects of NaCl and Na2SO4 salinity on Phragmites australis

    DEFF Research Database (Denmark)

    Pagter, Majken; Bragato, Claudia; Malagoli, Mario

    2009-01-01

    Osmotic and ion-specific effects of NaCl and Na2SO4 on Phragmites australis (Cav.) Trin ex. Steud. were investigated in a laboratory experiment by examining effects of iso-osmotic solutions of NaCl and Na2SO4 on growth, osmolality of cell sap, proline content, elemental composition and gas exchange....... Plants were supplied with a control standard nutrient solution (Ψ = -0.09 MPa) or solutions of NaCl or Na2SO4 at water potentials of -0.50, -1.09 or -1.74 MPa. Salt treatments increased root concentrations of Na and S or Cl, whereas P. australis had efficient mechanisms for exclusion of Na and S...... and partly Cl ions from the leaves. Incomplete exclusion of Cl from the leaves may affect aboveground biomass production, which was significantly more reduced by NaCl than Na2SO4. Stomatal conductance was negatively influenced by decreasing water potentials caused by NaCl or Na2SO4, implying that a non...

  4. Polarization and collision velocity dependence of associative ionization in cold Na (3p)-Na(3p) collisions

    NARCIS (Netherlands)

    Meijer, H.A.J.

    1990-01-01

    We studied the polarization dependence of the associative ionization (AI) process Na(3p) + Na(3p) → Na2+ at collision velocities between 100 and 700 m/s (5 and 200 K), using linearly and circularly polarized light for the excitation. We found that the polarization dependence varies strongly in the

  5. Erythrocyte Na+/K+ ATPase activity measured with sup 23 Na NMR

    Energy Technology Data Exchange (ETDEWEB)

    Ouwerkerk, R.; van Echteld, C.J.; Staal, G.E.; Rijksen, G. (University Hospital, Utrecht (Netherland))

    1989-11-01

    A {sup 23}Na NMR assay for measurement of erythrocyte Na+/K+ ATPase activity is presented. Using the nonpermeant shift reagent dysprosium tripolyphosphate the signals of intra- and extracellular sodium are separated, enabling measurement of sodium fluxes nondestructively, without the need to physically separate the cells from their environment. By increasing membrane permeability with nystatin we have shown that the assay allows the detection of differences in membrane permeability. With low doses of nystatin the ouabain-sensitive sodium flux increased more than twofold. With high doses of nystatin the Na+/K+ pump could not prevent an almost total equilibration of intra- and extracellular sodium. All sodium that entered the cells remained NMR visible, proving that sodium influx can be measured quantitatively. {sup 31}P NMR spectra taken before and after the assay revealed a slight acidification of the cells and no significant change in ATP concentration. No evidence of Dy3+ entering the cell was observed.

  6. 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

  7. Molecular dynamics investigation of Na+ in Na2Ni2TeO6

    International Nuclear Information System (INIS)

    Sau, Kartik; Kumar, P. Padma

    2014-01-01

    An inter-atomic potential for Na 2 Ni 2 TeO 6 in the Parrinello- Rahman-Vashishta (PRV) model is parameterized empirically. The potential reproduces variety of structural and transport properties of that material in good agreement with recent experimental results. The study provides fresh insights on the migration channels and mechanism of Na + in the system

  8. Efeito do plasma de oxigênio na dentina previamente exposta ao NaOCl

    Directory of Open Access Journals (Sweden)

    Maíra do PRADO

    Full Text Available Resumo Introdução O tratamento de plasma é uma tecnologia eficaz que pode manter as propriedades internas dos materiais inalteradas após o tratamento, modificando apenas a superfície. Objetivo Avaliar o efeito do plasma de oxigênio na dentina previamente exposta ao NaOCl 6%. Material e método Foram utilizados 60 incisivos bovinos. A coroa foi removida, a raiz foi dividida e as faces planificadas, totalizando 120 segmentos referentes ao terço cervical. As amostras foram divididas em dois grupos: controle (imersa em NaOCl 6%, lavada com água destilada, seca, imersa em EDTA 17%, lavada e seca e plasma de oxigênio (após tratamento descrito no grupo controle, plasma de oxigênio foi aplicado por 30 s. As amostras foram avaliadas qualitativamente em relação à topografia por microscopia eletrônica de varredura, utilizando-se microfotografias com ampliação de 1.000×. O goniômetro Ramé-hart foi utilizado para a mensuração do ângulo de contato entre as superfícies e as seguintes soluções foram utilizadas: água, etilenoglicol e di-iodometano. Em seguida, a energia de superfície, representada pelas componentes polar e dispersiva, foi calculada. Avaliou-se também o escoamento dos cimentos Pulp Canal Sealer EWT (PCS e Real Sal SE (RS na superfície dentinária. Os dados foram analisados estatisticamente utilizando os testes Kruskal-Wallis e Mann-Whitney U (p<0,05. Resultado O tratamento com plasma levou à formação de uma camada semelhante à smear layer na superfície dentinária. Este tratamento levou a um aumento da energia de superfície e da componente polar, favorecendo a hidrofilicidade da superfície. Entretanto, desfavoreceu o escoamento do cimento PCS e não influenciou no escoamento do cimento RS. Conclusão O plasma de oxigênio ocasionou mudanças topográficas na superfície dentinária, favorecendo a hidrofilicidade desta. Contudo, não favoreceu o escoamento dos cimentos endodônticos na dentina.

  9. Phase formation in the systems ZrO2-H2SO4-Na2SO4 (NaCl)-H2O

    International Nuclear Information System (INIS)

    Sozinova, Yu.P.; Motov, D.L.; Rys'kina, M.P.

    1988-01-01

    Formation of solid phases in the systems ZrO 2 - H 2 SO 4 - Na 2 SO 4 (NaCl) - H 2 O at 25 and 75 deg C is studied. Three basic Na 2 Zr(OH) 2 (SO 4 ) 2 x (0.2 - 0.4)H 2 O, NaZrOH(SO 4 ) 2 x H 2 O, NaZrO 0.5 (OH) 2 SO 4 x 2H 2 O and three normal sodium sulfatozirconates Na 2 Zr(SO 4 ) 3 x 3H 2 O, Na 4 Zr(SO 4 ) 4 x 3H 2 O, Na 6 Zr(SO 4 ) 5 x 4H 2 O have been isolated, their solubility and crystal optical properties are determined

  10. Modification of NaK (Na and K) dissolution device at the L.E.C.I

    International Nuclear Information System (INIS)

    Mansard, Bernard; Ducas, Serge; Riviere, Michel

    1969-12-01

    As three NaK dissolution devices had been operated since 1965 and as irradiation assemblies with a greater capacity (2 to 3 times) are now to be used, the modification of these dissolution devices is addressed. This requires a better control of the dissolution reaction (the NaK + alcohol reaction is highly exothermic and results in an effervescence which requires a greater volume). The objectives are therefore to delay the dissolution, to trigger it, to stop it, to control it at will, and to release heat. The new device is then described with its vessel, its cap, its ball valve, and its two tight sleeves. The operation principle is described, as well as the NaK draining process, and the NaK dissolution. Safety, time saving and raw matter saving issues are finally outlined

  11. OGLAŠEVANJE NA FACEBOOKU V SLOVENIJI

    OpenAIRE

    Dobnik, Monja

    2013-01-01

    Danes so zahvaljujoč napredni mobilni tehnologiji družbena omrežja z nami na vsakem koraku. Facebook (FB) se po priljubljenosti uvršča v sam vrh družbenih omrežij in glede na to, da ga uporablja že več kot milijarda zemljanov, ponuja tudi odlične trg za oglaševanje. To so ugotovili tudi slovenski podjetniki. V diplomski nalogi je predstavljeno, kako na FB oglašujejo nekatera slovenska podjetja, s pomočjo spletnega vprašalnika pa je ugotovljeno tudi, kaj o oglasih na FB menijo njegovi uporabni...

  12. Myocardial Na,K-ATPase: Clinical aspects

    Science.gov (United States)

    Kjeldsen, Keld

    2003-01-01

    The specific binding of digitalis glycosides to Na,K-ATPase is used as a tool for Na,K-ATPase quantification with high accuracy and precision. In myocardial biopsies from patients with heart failure, total Na,K-ATPase concentration is decreased by around 40%; a correlation exists between a decrease in heart function and a decrease in Na,K-ATPase concentration. During digitalization, around 30% of remaining pumps are occupied by digoxin. Myocardial Na,K-ATPase is also influenced by other drugs used for the treatment of heart failure. Thus, potassium loss during diuretic therapy has been found to reduce myocardial Na,K-ATPase, whereas angiotensin-converting enzyme inhibitors may stimulate Na,K pump activity. Furthermore, hyperaldosteronism induced by heart failure has been found to decrease Na,K-ATPase activity. Accordingly, treatment with the aldosterone antagonist, spironolactone, may also influence Na,K-ATPase activity. The importance of Na,K pump modulation with heart disease, inhibition in digitalization and other effects of medication should be considered in the context of sodium, potassium and calcium regulation. It is recommended that digoxin be administered to heart failure patients who, after institution of mortality-reducing therapy, still have heart failure symptoms, and that the therapy be continued if symptoms are revealed or reduced. Digitalis glycosides are the only safe inotropic drugs for oral use that improve hemodynamics in heart failure. An important aspect of myocardial Na,K pump affection in heart disease is its influence on extracellular potassium (Ke) homeostasis. Two important aspects should be considered: potassium handling among myocytes, and effects of potassium entering the extracellular space of the heart via the bloodstream. It should be noted that both of these aspects of Ke homeostasis are affected by regulatory aspects, eg, regulation of the Na,K pump by physiological and pathophysiological conditions, as well as by medical

  13. Advancement of technology towards developing Na-ion batteries

    Science.gov (United States)

    Jamesh, Mohammed Ibrahim; Prakash, A. S.

    2018-02-01

    The Na-ion-batteries are considered much attention for the next-generation power-sources due to the high abundance of Na resources that lower the cost and become the alternative for the state of the art Li-ion batteries in future. In this review, the recently reported potential cathode and anode candidates for Na-ion-batteries are identified in-light-of-their high-performance for the development of Na-ion-full-cells. Further, the recent-progress on the Na-ion full-cells including the strategies used to improve the high cycling-performance (stable even up-to 50000 cycles), operating voltage (even ≥ 3.7 V), capacity (>350 mAhg-1 even at 1000 mAg-1 (based-on-mass-of-the-anode)), and energy density (even up-to 400 Whkg-1) are reviewed. In addition, Na-ion-batteries with the electrodes containing reduced graphene oxide, and the recent developments on symmetric Na-ion-batteries are discussed. Further, this paper identifies the promising Na-ion-batteries including the strategies used to assemble full-cell using hard-carbon-anodes, Na3V2(PO4)3 cathodes, and other-electrode-materials. Then, comparison between aqueous and non-aqueous Na-ion-batteries in terms of voltage and energy density has been given. Later, various types of electrolytes used for Na-ion-batteries including aqueous, non-aqueous, ionic-liquids and solid-state electrolytes are discussed. Finally, commercial and technological-developments on Na-ion-batteries are provided. The scientific and engineering knowledge gained on Na-ion-batteries afford conceivable development for practical application in near future.

  14. Negative electrodes for Na-ion batteries.

    Science.gov (United States)

    Dahbi, Mouad; Yabuuchi, Naoaki; Kubota, Kei; Tokiwa, Kazuyasu; Komaba, Shinichi

    2014-08-07

    Research interest in Na-ion batteries has increased rapidly because of the environmental friendliness of sodium compared to lithium. Throughout this Perspective paper, we report and review recent scientific advances in the field of negative electrode materials used for Na-ion batteries. This paper sheds light on negative electrode materials for Na-ion batteries: carbonaceous materials, oxides/phosphates (as sodium insertion materials), sodium alloy/compounds and so on. These electrode materials have different reaction mechanisms for electrochemical sodiation/desodiation processes. Moreover, not only sodiation-active materials but also binders, current collectors, electrolytes and electrode/electrolyte interphase and its stabilization are essential for long cycle life Na-ion batteries. This paper also addresses the prospect of Na-ion batteries as low-cost and long-life batteries with relatively high-energy density as their potential competitive edge over the commercialized Li-ion batteries.

  15. Corpo e sexualidade na gravidez

    Directory of Open Access Journals (Sweden)

    Natalúcia Matos Araújo

    2012-06-01

    Full Text Available Estudo etnográfico que teve como objetivo compreender como as gestantes vivenciam os processos fisiológicos do seu corpo durante a gestação e a sua repercussão na sexualidade. A pesquisa envolveu sete mulheres residentes em bairro popular de São Paulo. Na coleta de dados, utilizou-se observação participante e entrevista com questões norteadoras. Os dados foram apresentados na forma de narrativa e posteriormente organizados nas categorias: Percebendo as transformações corporais; Convivendo com as mudanças no corpo; Sentimentos e sensações na vida sexual durante a gestação e imaginando o corpo e a sexualidade após a gestação. As mulheres referiram-se às transformações do corpo como desconfortos e expressaram a preocupação de que fossem definitivas. Expressaram o desejo de que, após o parto, o corpo volte a ser como era e que volte a sentir desejo sexual. O reconhecimento destes fatos constitui-se numa ferramenta primordial na adequação das práticas profissionais.

  16. Comparison of the effectiveness of seven amiloride congeners as inhibitors of Na/H and Na/Ca antiport in cultured smooth muscle cells

    International Nuclear Information System (INIS)

    Smith, L.; Higgins, B.L.; Cragoe, E.J. Jr.; Smith, J.B.

    1987-01-01

    The authors cultured smooth muscle cells from rat aorta and assayed Na/Ca antiport by measuring the initial rate of 45 Ca influx in Na-loaded cells. Na/H antiport was assayed by measuring the initial rate of 22 Na influx in acid-loaded cells. The external medium was the same for both assays except Na was 10 mM for Na/H antiport and O for the Na/Ca antiport assay. The dose of each congener that caused 50% inhibition (I 50 ) was calculated using a log-log median effect plot. The linear regression coefficients ranged from 0.916 to 0.998. Of all the compounds tested only dimethylbenzamil is more potent as an inhibitor of Na/Ca compared to Na/H antiport

  17. Presoja notranjih kontrol pri obračunu davka na dodano vrednost na primeru "Podjetja x"

    OpenAIRE

    Majcen, Borut

    2016-01-01

    Poslovanje podjetja si je ob odsotnosti notranjih kontrol nemogoče predstavljati. Podjetja so podvržena raznim tveganjem, še posebej v današnjih razmerah globalnega poslovanja, ko se podjetja soočajo z vedno novimi izzivi, kar prinaša tudi nova tveganja. Najučinkovitejši ukrep za obvladovanje tveganj predstavlja vzpostavitev sistema notranjih kontrol. Obvladovanje tveganj pa ne poteka samo na ravni podjetja kot celote, ampak je prisotno na vseh področjih delovanja podjetja, torej tudi na p...

  18. Culturas morais e políticas de desenvolvimento na noruega e na união europeia

    Directory of Open Access Journals (Sweden)

    Maria Macedo Barroso

    2014-06-01

    Full Text Available A partir de um diálogo entre os casos da Noruega e da União Europeia, pretendemos analisar a combinação de diferentes fatores e escalas de processos sociais (individuais, institucionais e de unidades políticas nacionais e supranacionais, estruturantes na formação dos sentidos sociais do desenvolvimento, notadamente das relações entre princípios morais e trocas interessadas, constitutivas das "culturas morais" dos universos analisados. Na perspectiva dos indivíduos, observaremos pela lente do caso da UE as motivações, vocações e histórias de vida dos "profissionais do desenvolvimento", bem como as razões da adesão da opinião pública às ações de cooperação internacional. Na escala institucional, abordaremos, nos dois casos, os modelos político-administrativos utilizados pela burocracia do desenvolvimento, e as lógicas dos diferentes grupos organizados para disputar seus recursos, no caso da Noruega. Na dimensão dos Estados, analisaremos a lógica das políticas nacionais e internacionais sob as quais são negociadas as intervenções de cooperação bilateral e/ou multilaterais tanto na Noruega quanto na UE.

  19. Intermittent Hypoxia Inhibits Na+-H+ Exchange-Mediated Acid Extrusion Via Intracellular Na+ Accumulation in Cardiomyocytes

    Directory of Open Access Journals (Sweden)

    Huai-Ren Chang

    2018-04-01

    Full Text Available Background/Aims: Intermittent hypoxia (IH has been shown to exert preconditioning-like cardioprotective effects. It also has been reported that IH preserves intracellular pH (pHi during ischemia and protects cardiomyocytes against ischemic reperfusion injury. However, the exact mechanism is still unclear. Methods: In this study, we used proton indicator BCECF-AM to analyze the rate of pHi recovery from acidosis in the IH model of rat neonatal cardiomyocytes. Neonatal cardiomyocytes were first treated with repetitive hypoxia-normoxia cycles for 1-4 days. Cells were then acid loaded with NH4Cl, and the rate of pHi recovery from acidosis was measured. Results: We found that the pHi recovery rate from acidosis was much slower in the IH group than in the room air (RA group. When we treated cardiomyocytes with Na+-H+ exchange (NHE inhibitors (Amiloride and HOE642 or Na+-free Tyrode solution during the recovery, there was no difference between RA and IH groups. We also found intracellular Na+ concentration ([Na+]i significantly increased after IH exposure for 4 days. However, the phenomenon could be abolished by pretreatment with ROS inhibitors (SOD and phenanathroline, intracellular calcium chelator or Na+-Ca2+ exchange (NCX inhibitor. Furthermore, the pHi recovery rate from acidosis became faster in the IH group than in the RA group when inhibition of NCX activity. Conclusions: These results suggest that IH would induce the elevation of ROS production. ROS then activates Ca2+-efflux mode of NCX and results in intracellular Na+ accumulation. The rise of [Na+]i further inhibits the activity of NHE-mediated acid extrusion and retards the rate of pHi recovery from acidosis during IH.

  20. Elastic Coulomb breakup of 34Na

    Science.gov (United States)

    Singh, G.; Shubhchintak, Chatterjee, R.

    2016-08-01

    Background: 34Na is conjectured to play an important role in the production of seed nuclei in the alternate r -process paths involving light neutron rich nuclei very near the β -stability line, and as such, it is important to know its ground state properties and structure to calculate rates of the reactions it might be involved in, in the stellar plasma. Found in the region of `island of inversion', its ground state might not be in agreement with normal shell model predictions. Purpose: The aim of this paper is to study the elastic Coulomb breakup of 34Na on 208Pb to give us a core of 33Na with a neutron and in the process we try and investigate the one neutron separation energy and the ground state configuration of 34Na. Method: A fully quantum mechanical Coulomb breakup theory within the architecture of post-form finite range distorted wave Born approximation extended to include the effects of deformation is used to research the elastic Coulomb breakup of 34Na on 208Pb at 100 MeV/u. The triple differential cross section calculated for the breakup is integrated over the desired components to find the total cross-section, momentum, and angular distributions as well as the average momenta, along with the energy-angular distributions. Results: The total one neutron removal cross section is calculated to test the possible ground state configurations of 34Na. The average momentum results along with energy-angular calculations indicate 34Na to have a halo structure. The parallel momentum distributions with narrow full widths at half-maxima signify the same. Conclusion: We have attempted to analyze the possible ground state configurations of 34Na and in congruity with the patterns in the `island of inversion' conclude that even without deformation, 34Na should be a neutron halo with a predominant contribution to its ground state most probably coming from 33Na(3 /2+)⊗ 2 p3 /2ν configuration. We also surmise that it would certainly be useful and rewarding to test our

  1. Osmotic and activity coefficients of aqueous NaTcO4 and NaReO4 solutions at 250C

    International Nuclear Information System (INIS)

    Boyd, G.E.

    1978-01-01

    Isopiestic vapor-pressure comparison experiments were performed with aqueous binary sodium perchlorate, pertechnetate, and perrhenate solutions to concentrations of approximately 8.5 m. Osmotic coefficients for these solutions and mean molal ionic activity coefficients for NaTcO 4 and NaReO 4 were derived from the isotonic molalities. Pitzer's treatment was applied to describe the concentration dependence of the osmotic coefficients of NaClO 4 , NaTcO 4 , and NaReO 4 , and the implications of the parameters derived from a least-squares fit are discussed in terms of solvent structure and interionic forces. 4 tables, 1 figure

  2. Energy levels of the single excited states in NaI and Na-like ions

    International Nuclear Information System (INIS)

    El-Sherbini, T.M.; Wahby, A.S.

    1987-08-01

    Energy levels of the single excited 1s 2 2s 2 2p 6 ns( 2 S), 1s 2 2s 2 2p 6 mp( 2 P), 1s 2 2s 2 2p 6 md( 2 D) and 1s 2 2s 2 2p 6 nf( 2 F); n=4-7, m=3-6 states for NaI and Na-like ions are calculated using the one configuration Hartree-Fock method. Good agreement is obtained between our results for the higher members of the NaI sequence and previous data from photo-absorption and beam foil experiments. (author). 11 refs, 3 figs, 9 tabs

  3. 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.

  4. Fabrication of implanted $^{22}$Na targets

    CERN Multimedia

    2002-01-01

    A knowledge of the $^{22}$Na(p,$\\gamma$)$^{23}$ Mg reaction rate is of significant astrophysical interest. In order to complete previous studies of this reaction, radioactive $^{22}$Na targets of high purity are required. We ask for support to fabricate these targets via the implantation technique at ISOLDE GPS (off—line mode) using $^{22}$Na nuclides in an Al matrix produced in Nov. 1990 at the PSI (Zürich). The $^{22}$Na nuclides are released and ionized in a surface ionisation source, mass-analyzed at ISOLDE GPS, and implanted in a Ni-Ta backing and a C—foil in a special implantation setup.

  5. Painful Na-channelopathies: an expanding universe.

    Science.gov (United States)

    Waxman, Stephen G

    2013-07-01

    The universe of painful Na-channelopathies--human disorders caused by mutations in voltage-gated sodium channels--has recently expanded in three dimensions. We now know that mutations of sodium channels cause not only rare genetic 'model disorders' such as inherited erythromelalgia and channelopathy-associated insensitivity to pain but also common painful neuropathies. We have learned that mutations of NaV1.8, as well as mutations of NaV1.7, can cause painful Na-channelopathies. Moreover, recent studies combining atomic level structural models and pharmacogenomics suggest that the goal of genomically guided pain therapy may not be unrealistic. Copyright © 2013 Elsevier Ltd. All rights reserved.

  6. Usmerjanje urbanega razvoja na mestni ravni

    Directory of Open Access Journals (Sweden)

    Mojca Šašek Divjak

    1999-01-01

    Full Text Available Kot je poudarjeno v predstavljenem načrtu Kopenhagna, mestni načrt ne more rešiti vseh planskih problemov mesta. Predstavljal naj bi predvideni red, ki pa se pogosto sproti podira glede na nepredvidena dogajanja v prostoru. Probleme je velikokrat treba reševati šele, ko se pokažejo. Zato mora biti mestni načrt zastavljen dovolj prilagodljivo in fleksibilno, da dovoljuje potrebne spremembe. Vendar mora kljub temu dati mestu trdne glavne usmeritve in s tem omogočiti, da meščani lahko izkoristijo priložnosti, ki jih nudi nova doba in uveljavljajo nove kvalitete bivanja.

  7. Velocity distribution and dimer formation in a Na/Na2 beam

    International Nuclear Information System (INIS)

    Bergmann, K.; Hefter, U.; Hering, P.

    1977-01-01

    Using the TOF via optical pumping method and the Doppler-shifted laser induced emission described previously, the authors have measured the parallel and perpendicular velocity distribution respectively for Na atoms and Na 2 molecules in a variety of individual quantum states. In addition they monitored the flux of molecules in specific states while changing the stagnation pressure. In all cases a significant dependence on the internal energy of the molecules was found. The goal of these experiments is to improve understanding of the beam dynamics and the dimer formation process. (Auth.)

  8. Angular distributions of photoelectrons from free Na clusters

    International Nuclear Information System (INIS)

    Wopperer, P.; Dinh, P. M.; Faber, B.; Reinhard, P.-G.; Suraud, E.

    2010-01-01

    We explore, from a theoretical perspective, photoelectron angular distributions (PADs) of the Na clusters Na 8 , Na 10 , Na 12 , Na 18 , Na 3 + , Na 11 + , Na 13 + , and Na 19 + . The basis of the description is the time-dependent local-density approximation (TDLDA), augmented by a self-interaction correction (SIC) to describe ionization properties correctly. The scheme is solved on a numerical grid in coordinate space with absorbing bounds. We assume for each cluster system an isotropic ensemble of free clusters and develop for the case of one-photon emission analytical formulas for computing the orientation-averaged PAD on the basis of a few TDLDA-SIC calculations for properly chosen reference orientations. It turns out that all the information in the averaged PAD is contained in one anisotropy parameter. We find that this parameter varies very little with system size, but as a whole is crucially influenced by the detailed ionic structure. We also make comparisons with direct orientation averaging and consider one example reaching outside the perturbative regime.

  9. The Na+ transport in gram-positive bacteria defect in the Mrp antiporter complex measured with 23Na nuclear magnetic resonance.

    Science.gov (United States)

    Górecki, Kamil; Hägerhäll, Cecilia; Drakenberg, Torbjörn

    2014-01-15

    (23)Na nuclear magnetic resonance (NMR) has previously been used to monitor Na(+) translocation across membranes in gram-negative bacteria and in various other organelles and liposomes using a membrane-impermeable shift reagent to resolve the signals resulting from internal and external Na(+). In this work, the (23)Na NMR method was adapted for measurements of internal Na(+) concentration in the gram-positive bacterium Bacillus subtilis, with the aim of assessing the Na(+) translocation activity of the Mrp (multiple resistance and pH) antiporter complex, a member of the cation proton antiporter-3 (CPA-3) family. The sodium-sensitive growth phenotype observed in a B. subtilis strain with the gene encoding MrpA deleted could indeed be correlated to the inability of this strain to maintain a lower internal Na(+) concentration than an external one. Copyright © 2013 Elsevier Inc. All rights reserved.

  10. Quatenary Na//F, Cl, CO3, MoO4 system

    International Nuclear Information System (INIS)

    Kochkarov, Zh.A.; Lok''yaeva, S.M.; Shurdumov, G.K.; Gasanaliev, A.M.; Trunin, A.S.

    1999-01-01

    Perspective in applied respect quatenary system (NaF) 2 -(NaCl)-Na 2 CO 3 -Na 2 MoO 4 being element of narrowing of more complex six-membered mutual Na//F, Cl, CO 3 , MoO 4 (WO 4 ) system is investigated by differential thermal analysis with the use of projection-thermographic method for the first time. Crystallization tree of Na//F, Cl, CO 3 , MoO 4 system is established. It is shown that this system by tetrahedrating (NaF) 2 -Na 2 CO 3 -Na 3 ClMoO 4 section is triangulated on two stable system: (NaF) 2 -Na 3 ClMoO 4 -Na 2 CO 3 -(NaCl) 2 and (NaF) 2 -Na 3 ClMoO 4 -Na 2 CO 3 -Na 2 MoO 4 . Phase single units are determined too. Coordinates of desired quatenary nonvariant points are calculated on analytical models of surfaces by mutual crystallization of two phases and are refined by differential thermal analysis [ru

  11. Experimental Study of Na based Titanium Nanofluid-Water Reaction

    Energy Technology Data Exchange (ETDEWEB)

    Park, Gunyeop; Kim, Soo Jae; Baek, Jehyun; Kim, Hyun Soo; Oh, Sun Ryung; Park, Hyun Sun; Kim, Moo Hwan [POSTECH, Pohang (Korea, Republic of)

    2015-10-15

    In KALIMER-600, a sodium-cooled fast reactor designed by KAERI, thermal energy is transported from high-temperature liquid Na (526 .deg. C at 0.1 MPa) to low temperature water (230 .deg. C at - 19.5 MPa) through a heat exchanger. If any leakage or rupture occurs during the operation of this heat exchanger, highly pressurized liquid water can penetrate into the liquid Na channels; this contact should instantly cause SWR. As reaction continues, liquid water is soon vaporized by pressure drop and huge amount of reaction heat. This generated water vapor expands large reaction area and increases sodium-water vapor reaction process. Therefore, the rapid generation of reaction product (like H{sub 2}) and water vapor increases the system pressure that can cause the system failure in SFR. To reduce this strong chemical reaction phenomena between Na and water, some we have focused on suppressing the chemical reactivity of liquid Na by dispersing nanoparticles (NPs). For the real application of NaTiNF, the pressure change induced by NaTiNF-water reaction is compared with Na-water reaction in the present study. NaTiNF contains 100nm of Ti NPs at 0.2 vol. %. The reaction rate of NaTiNF-water reaction is also investigated as reaction temperature increases. Sodium-water vapor reaction (SVR) will occur when an SWR accident occurs in SFR. In this manner, NaTiNF-water vapor reaction is experimentally performed for ensuring the suppression of chemical reactivity of NaTiNF in contact with water vapor. In the basic step for reducing risk of an SWR in SFR, we have experimentally verified the suppressed chemical reactivity of liquid sodium using Ti NPs through SWR and SVR experiments. In SWR, Na based titanium nanofluid (NaTiNF) shows lower pressure change than Na. As T{sub R} increases, P{sub max} in Na-water reaction increases while NaTiNF does not. The reaction rate of NaTiNF shows twice slower than that of Na. In SVR, NaTiNF shows slower temperature increase than Na. The distinct

  12. Phase equilibria in the NaF-CdO-NaPO{sub 3} system at 873 K and crystal structure and physico-chemical characterizations of the new Na{sub 2}CdPO{sub 4}F fluorophosphate

    Energy Technology Data Exchange (ETDEWEB)

    Aboussatar, Mohamed [Université Clermont Auvergne, Université Blaise Pascal, Institut de Chimie de Clermont-Ferrand, UMR 6296 CNRS, BP 10448, F-63000 Clermont-Ferrand (France); Laboratoire de Physico-Chimie de l’État Solide, Faculté des Sciences de Sfax, Université de Sfax, BP 1171, 3000 Sfax (Tunisia); Mbarek, Aïcha [Laboratoire de Chimie Industrielle, Ecole Nationale d’Ingénieurs de Sfax, Université de Sfax, BP W3038, 3000 Sfax (Tunisia); Naili, Houcine [Laboratoire de Physico-Chimie de l’État Solide, Faculté des Sciences de Sfax, Université de Sfax, BP 1171, 3000 Sfax (Tunisia); El-Ghozzi, Malika [Université Clermont Auvergne, Université Blaise Pascal, Institut de Chimie de Clermont-Ferrand, UMR 6296 CNRS, BP 10448, F-63000 Clermont-Ferrand (France); Chadeyron, Geneviève [Université Clermont Auvergne, Institut de Chimie de Clermont-Ferrand, UMR 6296 CNRS/UBP/SIGMA, BP 10448, F-63000 Clermont-Ferrand (France); Avignant, Daniel [Université Clermont Auvergne, Université Blaise Pascal, Institut de Chimie de Clermont-Ferrand, UMR 6296 CNRS, BP 10448, F-63000 Clermont-Ferrand (France); Zambon, Daniel, E-mail: Daniel.Zambon@univ-bpclermont.fr [Université Clermont Auvergne, Université Blaise Pascal, Institut de Chimie de Clermont-Ferrand, UMR 6296 CNRS, BP 10448, F-63000 Clermont-Ferrand (France)

    2017-04-15

    Isothermal sections of the diagram representing phase relationships in the NaF-CdO-NaPO{sub 3} system have been investigated by solid state reactions and powder X-ray diffraction. This phase diagram investigation confirms the polymorphism of the NaCdPO{sub 4} side component and the structure of the ß high temperature polymorph (orthorhombic, space group Pnma and unit cell parameters a=9.3118(2), b=7.0459(1), c=5.1849(1) Å has been refined. A new fluorophosphate, Na{sub 2}CdPO{sub 4}F, has been discovered and its crystal structure determined and refined from powder X-ray diffraction data. It exhibits a new 3D structure with orthorhombic symmetry, space group Pnma and unit cell parameters a=5.3731(1), b=6.8530(1), c=12.2691(2) Å. The structure is closely related to those of the high temperature polymorph of the nacaphite Na{sub 2}CaPO{sub 4}F and the fluorosilicate Ca{sub 2}NaSiO{sub 4}F but differs essentially in the cationic repartition since the structure is fully ordered with one Na site (8d) and one Cd site (4c). Relationships with other Na{sub 2}M{sup II}PO{sub 4}F (M{sup II}=Mg, Ca, Mn, Fe, Co, Ni) have been examined and the crystal-chemical and topographical analysis of these fluorophosphates is briefly reviewed. IR, Raman, optical and {sup 19}F, {sup 23}Na, {sup 31}P MAS NMR characterizations of Na{sub 2}CdPO{sub 4}F have been investigated. - Graphical abstract: The structure of the compound Na{sub 2}CdPO{sub 4}F, discovered during the study of the phase relationships in the NaF-CdO-NaPO{sub 3} system, has been determined and compared with other Na{sub 2}M{sup II}PO{sub 4}F fluorophosphates. - Highlights: • XRD analysis of the isothermal section of the NaF-CdO-NaPO{sub 3} system at 923 K. • Rietveld refinement of the high temperature polymorph β-NaCdPO{sub 4}. • Crystal structure of the new Na{sub 2}CdPO{sub 4}F fluorophosphate determined from powder XRD. • Crystal structure - composition relationships of Na{sub 2}M{sup II}PO{sub 4}F compounds

  13. Mechanochemical transformations in Li(Na)AlH4-Li(Na)NH2 systems

    International Nuclear Information System (INIS)

    Dolotko, Oleksandr; Zhang Haiqiao; Ugurlu, Ozan; Wiench, Jerzy W.; Pruski, Marek; Scott Chumbley, L.; Pecharsky, Vitalij

    2007-01-01

    Mechanochemical transformations of tetrahydroaluminates and amides of lithium and sodium have been investigated using gas volumetric analysis, X-ray powder diffraction, solid-state nuclear magnetic resonance (NMR) and transmission electron microscopy. In a transformation of LiAlH 4 and LiNH 2 taken in an 1:1 molar ratio, the amount of released hydrogen (6.6 wt.% after 30 min ball milling) was higher than in any known one pot mechanochemical process involving a hydrogen-containing solid. A total of 4.3 wt.% of hydrogen is released by the NaAlH 4 -NaNH 2 system after 60 min ball milling; and 5.2 wt.% H 2 is released when LiAlH 4 and NaNH 2 or NaAlH 4 and LiNH 2 are ball milled for 90 min and 120 min, respectively. All transformations proceed at room temperature. The mechanism of the overall transformation MAlH 4 (s) + MNH 2 (s) → 2MH(s) + AlN(s) + 2H 2 (g) was identified based on detailed spectroscopic analysis of the intermediate (M 3 AlH 6 ) and final products of the ball milling process

  14. Makosa Yanayofanywa na Wanafunzi Wanaojifunza Kiswahili kama ...

    African Journals Online (AJOL)

    Makala haya, yanashughulika na makosa ambayo hufanywa na wanafunzi wanaojifunza Kiswahili kama lugha ya pili katika shule za sekondari nchini Uganda. Mtafiti ameyaainisha makosa mbalimbali na kuyaeleza kiusahihi. Makala yanaeleza namna ambavyo makosa hayo hutokea. Yaani, kama ni makosa ...

  15. Učinak video igre "Flappy Bird" na adolescente

    OpenAIRE

    Horvat, Marija

    2018-01-01

    Ovaj diplomski rad nastoji predstaviti uvid u učinke videoigre Flappy Bird na adolescente, fokusirajući se pritom na to potiče li ona nasilno ponašanje te nastoji odgovoriti na pitanje koliko je ta videoigra bila popularna među adolescentima u Hrvatskoj te po čemu je smatraju posebnom, tj. specifičnom. U tu svrhu provedeno je anketno istraživanje, a isti anketni upitnik proveden je na terenu i putem interneta te su uspoređeni rezultati. Anketni upitnik konstruiran je na način da se prvi dio u...

  16. Perinatal Na+ Overload Programs Raised Renal Proximal Na+ Transport and Enalapril-Sensitive Alterations of Ang II Signaling Pathways during Adulthood

    Science.gov (United States)

    Cabral, Edjair V.; Vieira-Filho, Leucio D.; Silva, Paulo A.; Nascimento, Williams S.; Aires, Regina S.; Oliveira, Fabiana S. T.; Luzardo, Ricardo; Vieyra, Adalberto; Paixão, Ana D. O.

    2012-01-01

    Background High Na+ intake is a reality in nowadays and is frequently accompanied by renal and cardiovascular alterations. In this study, renal mechanisms underlying perinatal Na+ overload-programmed alterations in Na+ transporters and the renin/angiotensin system (RAS) were investigated, together with effects of short-term treatment with enalapril in terms of reprogramming molecular alterations in kidney. Methodology/Principal Findings Male adult Wistar rats were obtained from dams maintained throughout pregnancy and lactation on a standard diet and drinking water (control) or 0.17 M NaCl (saline group). Enalapril (100 mg/l), an angiotensin converting enzyme inhibitor, was administered for three weeks after weaning. Ninety day old offspring from dams that drank saline presented with proximal tubules exhibiting increased (Na++K+)ATPase expression and activity. Ouabain-insensitive Na+-ATPase activity remained unchanged but its response to angiotensin II (Ang II) was lost. PKC, PKA, renal thiobarbituric acid reactive substances (TBARS), macrophage infiltration and collagen deposition markedly increased, and AT2 receptor expression decreased while AT1 expression was unaltered. Early treatment with enalapril reduced expression and activity of (Na++K+)ATPase, partially recovered the response of Na+-ATPase to Ang II, and reduced PKC and PKA activities independently of whether offspring were exposed to high perinatal Na+ or not. In addition, treatment with enalapril per se reduced AT2 receptor expression, and increased TBARS, macrophage infiltration and collagen deposition. The perinatally Na+-overloaded offspring presented high numbers of Ang II-positive cortical cells, and significantly lower circulating Ang I, indicating that programming/reprogramming impacted systemic and local RAS. Conclusions/Significance Maternal Na+ overload programmed alterations in renal Na+ transporters and in its regulation, as well as severe structural lesions in adult offspring. Enalapril

  17. alpha-Adducin mutations increase Na/K pump activity in renal cells by affecting constitutive endocytosis: implications for tubular Na reabsorption.

    Science.gov (United States)

    Torielli, Lucia; Tivodar, Simona; Montella, Rosa Chiara; Iacone, Roberto; Padoani, Gloria; Tarsini, Paolo; Russo, Ornella; Sarnataro, Daniela; Strazzullo, Pasquale; Ferrari, Patrizia; Bianchi, Giuseppe; Zurzolo, Chiara

    2008-08-01

    Genetic variation in alpha-adducin cytoskeletal protein is implicated in the polymerization and bundling of actin and alteration of the Na/K pump, resulting in abnormal renal sodium transport and hypertension in Milan hypertensive rats and humans. To investigate the molecular involvement of alpha-adducin in controlling Na/K pump activity, wild-type or mutated rat and human alpha-adducin forms were, respectively, transfected into several renal cell lines. Through multiple experimental approaches (microscopy, enzymatic assays, coimmunoprecipitation), we showed that rat and human mutated forms increased Na/K pump activity and the number of pump units; moreover, both variants coimmunoprecipitate with Na/K pump. The increased Na/K pump activity was not due to changes in its basolateral localization, but to an alteration of Na/K pump residential time on the plasma membrane. Indeed, both rat and human mutated variants reduced constitutive Na/K pump endocytosis and similarly affected transferrin receptor trafficking and fluid-phase endocytosis. In fact, alpha-adducin was detected in clathrin-coated vesicles and coimmunoprecipitated with clathrin. These results indicate that adducin, besides its modulatory effects on actin cytoskeleton dynamics, might play a direct role in clathrin-dependent endocytosis. The constitutive reduction of the Na/K pump endocytic rate induced by mutated adducin variants may be relevant in Na-dependent hypertension.

  18. VPLIV OSEBNOSTI NA STILE VODENJA

    OpenAIRE

    Vučak, Petra

    2009-01-01

    Nekatere naše vrline krasijo zlate lastnosti, druge pa kvarijo sivi odtenki. Če bi ljudje razumeli in spoznali svojo osebnost, ter osebnostne tipe drugih ljudi, bi se problemi pri komunikaciji občutno zmanjšali. Takrat bi namreč lažje uvideli, zakaj je nekdo reagiral na način, kot je ali zakaj je nekdo dejal to, kar je. Smisel tega je, da spoznamo svoje dobre lastnosti, ki jih lahko še bolj razvijemo, slabe pa poskušamo nadzorovati in tako zmanjšati njihov vpliv. Iskanje uspešnih in učink...

  19. VPLIV CENE NA ZADOVOLJSTVO IN ZVESTOBO UPORABNIKOV TELEKOMUNIKACIJSKIH STORITEV

    OpenAIRE

    Majcen, Mateja

    2016-01-01

    Cena izdelka ali storitve, ki jo plača uporabnik, ima pomemben vpliv na zadovoljstvo ali nezadovoljstvo uporabnika z uporabo tega izdelka ali storitve in posledično na zadovoljstvo do podjetja. Glede na to, da se različni avtorji strinjajo in to tudi dokazujejo z raziskavami, zadovoljstvo nedvoumno vpliva na zvestobo uporabnika, zvestoba pa na dolgoročno uspešnost podjetja, smo v delu ugotavljali, kako sama cena storitve vpliva na zadovoljstvo in kako posredno preko zadovoljstva vpliva na zve...

  20. NaI(Tl) electron energy resolution

    CERN Document Server

    Mengesha, W

    2002-01-01

    NaI(Tl) electron energy resolution eta sub e was measured using the Modified Compton Coincidence Technique (MCCT). The MCCT allowed detection of nearly monoenergetic internal electrons resulting from the scattering of incident 662 keV gamma rays within a primary NaI(Tl) detector. Scattered gamma rays were detected using a secondary HPGe detector in a coincidence mode. Measurements were carried out for electron energies ranging from 16 to 438 keV, by varying the scattering angle. Measured HPGe coincidence spectra were deconvolved to determine the scattered energy spectra from the NaI(Tl) detector. Subsequently, the NaI(Tl) electron energy spectra were determined by subtracting the energy of scattered spectra from the incident source energy (662 keV). Using chi-squared minimization, iterative deconvolution of the internal electron energy spectra from the measured NaI(Tl) spectra was then used to determine eta sub e at the electron energy of interest. eta sub e values determined using this technique represent va...

  1. Quantitative (23) Na MRI of human knee cartilage using dual-tuned (1) H/(23) Na transceiver array radiofrequency coil at 7 tesla.

    Science.gov (United States)

    Moon, Chan Hong; Kim, Jung-Hwan; Zhao, Tiejun; Bae, Kyongtae Ty

    2013-11-01

    To develop quantitative dual-tuned (DT) (1) H/(23) Na MRI of human knee cartilage in vivo at 7 Tesla (T). A sensitive (23) Na transceiver array RF coil was developed at 7T. B1 fields generated by the transceiver array coil were characterized and corrected in the (23) Na images. Point spread function (PSF) of the (23) Na images was measured, and the signal decrease due to partial-volume-effect was compensated in [(23) Na] quantification of knee cartilage. SNR and [(23) Na] in anterior femoral cartilage were measured from seven healthy subjects. SNR of (23) Na image with the transceiver array coil was higher than that of birdcage coil. SNR in the cartilage at 2-mm isotropic resolution was 26.80 ± 3.69 (n = 7). B1 transmission and reception fields produced by the DT coil at 7T were similar to each other. Effective full-width-half-maximum of (23) Na image was ∼5 mm at 2-mm resolution. Mean [(23) Na] was 288.13 ± 29.50 mM (n = 7) in the anterior femoral cartilage of normal subjects. We developed a new high-sensitivity (23) Na RF coil for knee MRI at 7T. Our (1) H/(23) Na MRI allowed quantitative measurement of [(23) Na] in knee cartilage by measuring PSF and cartilage thickness from (23) Na and (1) H image, respectively. Copyright © 2013 Wiley Periodicals, Inc.

  2. Razvitak naselja na kvarnerskim otocima - primjer Dobrinja

    Directory of Open Access Journals (Sweden)

    Marijan Bradanović

    2012-12-01

    Full Text Available Na dosad slabo poznatom i sa stajališta povijesti umjetnosti još posve neobrađenom primjeru Dobrinja na otoku Krku, raspravlja se o razvitku naselja na kvarnerskim otocima. Uz isticanje štetnosti dosad prevladavajućih uopćavanja, karakteristični položaj i razvitak Dobrinja tumače se u širem, komparativnom kontekstu. Analiziraju se prostiranje i obilježja pojedinih dijelova ovog naselja, a naglasak je na vremenu kasnog srednjeg i ranijeg novog vijeka. Tada je najuži dio povijesnog središta Dobrinja poprimio čvrstu, na tlorisnoj osnovi i danas, usprkos opsežnim pregradnjama i arhitektonskim preinakama, jasno uočljivu, urbanu fizionomiju.

  3. 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

  4. Investigation of sodalites for conditioning halide salts (NaCl and NaI): Comparison of two synthesis routes

    Energy Technology Data Exchange (ETDEWEB)

    Bardez, Isabelle; Campayo, Lionel; Rigaud, Danielle; Chartier, Myriam; Calvet, Aurelie [CEA, Laboratoire d' Etudes des Materiaux Ceramiques pour le Conditionnement, Site de Marcoule, Batiment 208, B.P. 17171, 30207 Bagnols sur Ceze cedex (France)

    2008-07-01

    Sodalites with the general formula Na{sub 8}Al{sub 6}Si{sub 6}O{sub 24}X{sub 2} (where X = Cl or I) were investigated for ceramic conditioning of halide salts (NaCl and NaI). Because of the tendency of halides to volatilize at high temperature, two synthesis routes were tested to optimize the halide content in the sodalite phase. The first is based on heating at high temperature of a [nepheline NaAlSiO{sub 4} + salt] mixture prepared by a dry process. The second, performed at low temperature, consists of the reaction in aqueous media between kaolinite (Al{sub 2}Si{sub 2}O{sub 5}(OH){sub 4}), sodium hydroxide (NaOH) and the salt. The present study compares these two syntheses and examines differences between chloro-sodalite and iodo-sodalite based on X-ray diffraction and infrared spectroscopy. The next step will consist in sintering the resulting powder samples to obtain dense ceramics. (authors)

  5. Dissolution of targets for the production of Mo-99: Part 1. Influence of NaOH concentration and the addition of NaNO3 and NaNO2 on the dissolution time

    International Nuclear Information System (INIS)

    Camilo, Ruth L.; Araujo, Izilda da C.; Mindrisz, Ana C.; Forbicini, Christina A.L.G. de O.

    2011-01-01

    Faced with global crisis in the production of radioisotope 99 Mo, which product of decay, 99 mTc, is the tracer element most often used in nuclear medicine and accounts for about 80% of all diagnostic procedures in vivo, since September 2008 Brazil is developing the project called Brazilian Multipurpose Reactor (RMB). Within the Brazilian Nuclear Program (PNB) the construction of the RMB, is seen as a long term solution to meet all domestic demand relative to the supply of radioisotopes and radiopharmaceuticals. In the process to be studied to obtain 99 Mo from irradiated UA1 x -A1 LEU targets employing alkaline dissolution, processing time should be minimized, considering the short half life of 99 Mo and 99 mTc, about 66 h and 6 h, respectively. That makes dissolution time a significant factor in the development of the process. This paper presents the results of alkaline dissolution of scraps of Al, used to simulate the dissolution process of UA1 x -A1 targets. Al corresponds to about 79% of the total weight of the UA1 x -A1 target. The effect of NaOH concentration on dissolution time for the interval of 1 to 3.5 mol.L-1 was studied, keeping the molar ratio in 1Al:2.16NaOH and the initial temperature of 88 degree C. The influence of reagent composition over dissolution time was studied using three different solutions: a) 3 mol.L -1 NaOH, b) 3 mol.L -1 NaOH/NaNO 3 and c) 3 mol.L -1 NaOH/NaNO 2 , keeping the same molar ratio and temperature. The results showed that the dissolution time decreases with increasing NaOH concentration and the addition of NaNO 3 or NaNO 2 in the NaOH solution reduces both dissolution time and volume of gases released. (author)

  6. Magnetic upconverting fluorescent NaGdF4:Ln3+ and iron-oxide@NaGdF4:Ln3+ nanoparticles

    Science.gov (United States)

    Shrivastava, Navadeep; Rocha, Uéslen; Muraca, Diego; Jacinto, Carlos; Moreno, Sergio; Vargas, J. M.; Sharma, S. K.

    2018-05-01

    Microwave assisted solvothermal method has been employed to synthesize multifunctional upconverting β-NaGdF4:Ln3+ and magnetic-upconverting Fe3O4/γ-Fe2O3@NaGdF4:Ln3+ (Ln = Yb and Er) nanoparticles. The powder x-ray diffraction data confirms the hexagonal structure of NaGdF4:Ln3+ and high resolution transmission electron microscopy shows the formation of rod shaped NaGdF4:Ln3+ (˜ 20 nm) and ovoid shaped Fe3O4/γ-Fe2O3@NaGdF4:Ln3+ (˜ 15 nm) nanoparticles. The magnetic hysteresis at 300 K for β-NaGdF4:Ln3+ demonstrates paramagnetic features, whereas iron-oxide@β-NaGdF4:Ln3+ exhibits superparamagnetic behavior along with a linear component at large applied field due to paramagnetic NaGdF4 matrix. Both nanoparticle samples provide an excellent green emitting [(2H11/2, 4S3/2)→4I15/2 (˜ 540 nm)] upconversion luminescence emission under excitation at 980 nm. The energy migration between Yb and Er in NaGdF4 matrix has been explored from 300-800 nm. Intensity variation of blue, green and red lines and the observed luminescence quenching due to the presence of Fe3O4/γ-Fe2O3 in the composite has been proposed. These kinds of materials contain magnetic and luminescence characteristics into single nanoparticle open new possibility for bioimaging applications.

  7. The plant vacuolar Na+/H+ antiport.

    Science.gov (United States)

    Barkla, B J; Apse, M P; Manolson, M F; Blumwald, E

    1994-01-01

    Salt stress imposes severe limitations on plant growth, however, the extent of growth reduction depends upon the soil salinity level and the plant species. One of the mechanisms employed by salt tolerant plants is the effective vacuolar compartmentalization of sodium. The sequestration of sodium into the vacuole occurs by the operation of a Na+/H+ antiport located at the tonoplast. Evidence for a plant vacuolar Na+/H+ antiport has been demonstrated in tissues, intact vacuoles and isolated tonoplast vesicles. In sugar beet cell suspensions, the activity of the vacuolar Na+/H+ antiport increased with increasing NaCl concentrations in the growth medium. This increased activity was correlated with the increased synthesis of a 170 kDa tonoplast polypeptide. In vivo labelling of tonoplast proteins showed the enhanced synthesis of the 170 kDa polypeptide not only upon exposure of the cells to salt, but also when the cells were grown in the presence of amiloride. Exposure of the cells to amiloride also resulted in increased vacuolar Na+/H+ antiport activity. Polyclonal antibodies raised against the 170 kDa polypeptide almost completely inhibited the antiport activity, suggesting the association of this protein with the plant vacuolar Na+/H+ antiport. Antibodies against the Na+/H+ antiport-associated polypeptide were used to screen a Beta lambda ZAP expression library. A partial clone of 1.65 kb was sequenced and found to encode a polypeptide with a putative transmembrane domain and a large hydrophilic C terminus. This clone showed no homology to any previously cloned gene at either the nucleic acid or the amino acid level.

  8. Correlation of the Na2SiO3 to NaOH Ratios and Solid to Liquid Ratios to the Kedah’s Soil Strength

    Directory of Open Access Journals (Sweden)

    Nur Hamzah Hazamaah

    2016-01-01

    Full Text Available Geopolymer was used for the soil stabilization of Kedah’s soil at different ratios of solid to liquid and Na2SiO3 to NaOH in order to achieve the desired compressive strength. The geopolymerization process which produces an aluminosilicate gel was occurred due to the mixing of Kedah’s soil and fly ash with Na2SiO3 and NaOH. Soil stabilization by geopolymer was synthesized by the activation of fly ash and Kedah’s soil with Na2SiO3 and NaOH at different ratios of solid to liquid (1.5, 2.0, 2.5 and 3.0 and Na2SiO3 to NaOH (0.5, 1.0, 1.5, 2.0, 2.5 and 3.0 at a specific constant concentration of NaOH solution of 6M. The compressive strength up to 5.12 MPa was obtained at 3.0 of solid to liquid ratio and 2.5 of Na2SiO3 to NaOH ratio in 7 days curing at room temperature.

  9. Near resonant charge transfer in Na(4D)+K+ → Na++K*: Optical pumping of the Na(4D) state and energy dependence of rank 4 alignment

    International Nuclear Information System (INIS)

    Campbell, E.E.B.; Huelser, H.; Witte, R.; Hertel, I.V.

    1990-01-01

    Rank 4 alignment has been observed in a quasi one electron system. Relative charge transfer cross sections of the Na 4dσ, 4dπ and 4dδ sublevels for the K + +Na(4D)→K * +Na + system have been measured. A strong energy dependence is observed. The results at energies less than 1 keV may be attributed to rotational coupling of the Na 4dπ state to the K 4fδ state. The Na atom is excited in a two-step process, the first step being excitation to the 3 2 P 3/2 level with a two-mode laser to pump from both hyperfine levels of the ground state simultaneously. This two-mode laser is described in detail. The optical pumping problem is solved using rate equations. The general formula for describing the scattering intensity for cylindrical symmetry, in terms of multipole moments, for atoms excited by two linearly polarised lasers is derived and used to evaluate the experimental results. (orig.)

  10. Thermodynamic description of Tc(iv) solubility and carbonate complexation in alkaline NaHCO3-Na2CO3-NaCl systems.

    Science.gov (United States)

    Baumann, A; Yalçıntaş, E; Gaona, X; Polly, R; Dardenne, K; Prüßmann, T; Rothe, J; Altmaier, M; Geckeis, H

    2018-03-28

    The solubility of 99 Tc(iv) was investigated in dilute to concentrated carbonate solutions (0.01 M ≤ C tot ≤ 1.0 M, with C tot = [HCO 3 - ] + [CO 3 2- ]) under systematic variation of ionic strength (I = 0.3-5.0 M NaHCO 3 -Na 2 CO 3 -NaCl-NaOH) and pH m (-log[H + ] = 8.5-14.5). Strongly reducing conditions (pe + pH m ≈ 2) were set with Sn(ii). Carbonate enhances the solubility of Tc(iv) in alkaline conditions by up to 3.5 log 10 -units compared to carbonate-free systems. Solvent extraction and XANES confirmed that Tc was kept as +IV during the timeframe of the experiments (≤ 650 days). Solid phase characterization performed by XAFS, XRD, SEM-EDS, chemical analysis and TG-DTA confirmed that TcO 2 ·0.6H 2 O(am) controls the solubility of Tc(iv) under the conditions investigated. Slope analysis of the solubility data in combination with solid/aqueous phase characterization and DFT calculations indicate the predominance of the species Tc(OH) 3 CO 3 - at pH m ≤ 11 and C tot ≥ 0.01 M, for which thermodynamic and activity models are derived. Solubility data obtained above pH m ≈ 11 indicates the formation of previously unreported Tc(iv)-carbonate species, possibly Tc(OH) 4 CO 3 2- , although the likely formation of additional complexes prevents deriving a thermodynamic model valid for this pH m -region. This work provides the most comprehensive thermodynamic dataset available for the system Tc 4+ -Na + -Cl - -OH - -HCO 3 - -CO 3 2- -H 2 O(l) valid under a range of conditions relevant for nuclear waste disposal.

  11. Stimulation of Na+/K+ ATPase activity and Na+ coupled glucose transport by β-catenin

    International Nuclear Information System (INIS)

    Sopjani, Mentor; Alesutan, Ioana; Wilmes, Jan; Dermaku-Sopjani, Miribane; Lam, Rebecca S.; Koutsouki, Evgenia; Jakupi, Muharrem; Foeller, Michael; Lang, Florian

    2010-01-01

    Research highlights: → The oncogenic transcription factor β-catenin stimulates the Na + /K + -ATPase. → β-Catenin stimulates SGLT1 dependent Na + , glucose cotransport. → The effects are independent of transcription. → β-Catenin sensitive transport may contribute to properties of proliferating cells. -- Abstract: β-Catenin is a multifunctional protein stimulating as oncogenic transcription factor several genes important for cell proliferation. β-Catenin-regulated genes include the serum- and glucocorticoid-inducible kinase SGK1, which is known to stimulate a variety of transport systems. The present study explored the possibility that β-catenin influences membrane transport. To this end, β-catenin was expressed in Xenopus oocytes with or without SGLT1 and electrogenic transport determined by dual electrode voltage clamp. As a result, expression of β-catenin significantly enhanced the ouabain-sensitive current of the endogeneous Na + /K + -ATPase. Inhibition of vesicle trafficking by brefeldin A revealed that the stimulatory effect of β-catenin on the endogenous Na + /K + -ATPase was not due to enhanced stability of the pump protein in the cell membrane. Expression of β-catenin further enhanced glucose-induced current (Ig) in SGLT1-expressing oocytes. In the absence of SGLT1 Ig was negligible irrespective of β-catenin expression. The stimulating effect of β-catenin on both Na + /K + ATPase and SGLT1 activity was observed even in the presence of actinomycin D, an inhibitor of transcription. The experiments disclose a completely novel function of β-catenin, i.e. the regulation of transport.

  12. Explosive phenomena in heavily irradiated NaCl

    NARCIS (Netherlands)

    denHartog, HW; Vainshtein, DI; Matthews, GE; Williams, RT

    1997-01-01

    In heavily irradiated NaCl crystals explosive phenomena can be initiated during irradiation or afterwards when samples are heated to temperatures between 100 and 250 degrees C. During irradiation of NaCl Na and Cl-2 precipitates and void structures are produced along with the accumulation of stored

  13. Crystallographic characterization of cement pastes hydrated with NaCl; Caracterizacao cristalografica de pastas de cimento hidratadas com NaCl

    Energy Technology Data Exchange (ETDEWEB)

    Melo, Carina Gabriela de Melo e; Martinelli, Antonio Eduardo; Melo, Dulce Maria Araujo; Melo, Marcus Antonio de Freitas; Melo, Vitor Rodrigo de Melo e [Universidade Federal do Rio Grande do Norte (UFRN), Natal, RN (Brazil)

    2012-07-01

    One of the major current challenges faced by oil companies is the exploration of pre salt basins. Salt layers deposited upon the evaporation of ocean water and continental separation are mainly formed by NaCl and isolate immense oil reservoirs. The mechanical stability and zonal isolation of oil wells that run through salt layers must be fulfilled by cement sheaths saturated with NaCl to assure chemical compatibility between cement and salt layer. The present study aimed at evaluating the effect of NaCl addition on the hydration of oil well cement slurries as well as identifying the nature of crystalline phases present in the hardened cement. To that end, cement slurries containing NaCl were mixed, hardened and characterized by X-ray diffraction. The results revealed that the presence of NaCl affects the formation of hydration products by the presence of Friedel's salt. The intensity of the corresponding peaks increase as the contents of NaCl in the slurry increase. High concentrations of NaCl in Portland slurries increase the setting time of cement and the presence of Friedel's salt decreases the strength of the hardened cement. (author)

  14. Estereótipos na comunicação intercultural: o caso do intercâmbio cultural na PUCRS

    OpenAIRE

    Espindola, Polianne Merie

    2010-01-01

    Este é um estudo da estereotipia existente na comunicação intercultural. O objetivo é entender a natureza do estereótipo mental e seu papel na comunicação entre interlocutores de culturas distintas. Para tanto, observa os estudantes estrangeiros em programas de intercâmbio no campus da Pontifícia Universidade Católica do Rio Grande do Sul. O estudo define o conceito de estereótipo e explicita seu papel na comunicação intercultural; verifica sua relevância na construção das narrativas entre cu...

  15. VPLIV ULCEROZNEGA KOLITISA NA KAKOVOST ŽIVLJENJA

    OpenAIRE

    Dugi, Maja

    2015-01-01

    Pri vsaki bolezni je zelo pomembna kakovost življenja pacientov. Ulcerozni kolitis je kronična bolezen, ki je znana po obdobjih mirovanja in izbruhov, kar definitivno vpliva na posameznika, ki se s tem spopada. Sooča se z raznimi omejitvami, ki vplivajo na njegov vsakdan. Rezultati raziskave so pokazali, da je kakovost življenja bolnikov z ulceroznim kolitisom izrazito okrnjena. Ne le, da se spopadajo z bolečino, ampak tudi s psihičnimi in socialnimi posledicami, ki vplivajo na fizične aktivn...

  16. Análise do efeito imunomodulador da ouabaína na inflamação e nocicepção

    OpenAIRE

    Vasconcelos, Danielle Ingrid Bezerra de

    2011-01-01

    A Ouabaína é um glicosídeo cardiotônico, inibidor da Na+/K+-ATPase, utilizada na clínica para o tratamento de insuficiência cardíaca. Atualmente, sabe-se que essa substância é endógena, e capaz de interferir em várias funções fisiológicas, inclusive em diversos aspectos do sistema imunológico. Apesar disso, pouco se sabe sobre seu envolvimento em processos inflamatórios e nociceptivos. Neste trabalho, foi avaliada a atividade da Ouabaína na inflamação aguda desencadeada pela ad...

  17. Erythrocyte 22Na+ influx in hypertension

    International Nuclear Information System (INIS)

    Shalev, O.; Eaton, J.W.; Ben-Ishay, D.

    1984-01-01

    We assessed 22Na+ uptake by erythrocytes (RBC) from 38 individuals with essential hypertension and 37 healthy controls. All subjects were male, white, non-obese and with normal renal function, obviating sex, race, hormonal, ponderal and renal factors known to influence RBC Na+ handling. The mean +/- sem 22Na+ uptake of the patients was 284 +/- 16 mumole/liter RBC/hour while that of normal controls was 249 +/- 11 mumole/liter RBC/hour; although the difference reached borderline significance, individual values showed considerable overlap. Consequently, in our population, RBC 22Na+ uptake is not a reliable marker for essential hypertension. We believe that previous studies should be reassessed with regard to patients' characteristics and future studies employ rigorous criteria in selection of subjects

  18. O grotesco na imagem publicitária

    OpenAIRE

    Silva, Maria João Barros

    2013-01-01

    O significado da palavra grotesco teve um começo puramente artístico numa descoberta, de imagens de figuras humanas deformadas e alteradas. No entanto, este foi evoluindo e adotando novos significados mais amplos e concretos na atualidade. É possível encontrar vários exemplos do grotesco em várias plataformas, como no cinema, na televisão e na literatura. Neste sentido, para se poder proceder ao estudo desta temática é fundamental a conquista do conhecimento sobre o estatuto do grotesco na pu...

  19. Gravidez na adolescência: tendência na produção científica de enfermagem

    OpenAIRE

    Gurgel, Maria Glêdes Ibiapina; Alves, Maria Dalva Santos; Vieira, Neiva Francenely Cunha; Pinheiro, Patrícia Neyva da Costa; Barroso, Grasiela Teixeira

    2008-01-01

    A gravidez em adolescentes tem implicações biológica, psicológica, social, econômica e cultural. O estudo exploratório, descritivo e bibliográfico objetivou identificar as concepções da gravidez na adolescência, sujeito, vulnerabilidade e gênero, presentes na produção científica de Enfermagem. Foram selecionados intencionalmente quatro periódicos brasileiros e dois da América Latina indexados de 2002 a 2006 na Scientific Electronic Library. Dos 1.472 artigos identificados, 43 tinham como temá...

  20. Neutralization of Na2PO4: Reaction between Na3PO4 and CaCL2

    International Nuclear Information System (INIS)

    Xia Shenglan; Wang Luning

    1990-01-01

    The results of reaction Na 3 PO 4 with CaCl 2 in water at ambient and higher temperature are described. The reaction rate of Na 3 PO 4 with CaCl 2 is slow at ambient temperature and the reaction is complete at 260 deg C after 2 h. The products are Ca(OH) 2 and Ca 5 (PO 4 ) 3 (OH). The quantity of them is dependent upon the quanity of Na 3 PO 4 and CaCl 2 contained in water, all of them control pH of water

  1. Raman scattering and lattice stability of NaAlH{sub 4} and Na{sub 3}AlH{sub 6}

    Energy Technology Data Exchange (ETDEWEB)

    Yukawa, H. [Department of Materials Science and Engineering, Graduate School of Engineering, Nagoya University, Chikusa-Ku, Nagoya 464-8603 (Japan)], E-mail: hiroshi@numse.nagoya-u.ac.jp; Morisaku, N.; Li, Y.; Komiya, K.; Rong, R.; Shinzato, Y. [Department of Materials Science and Engineering, Graduate School of Engineering, Nagoya University, Chikusa-Ku, Nagoya 464-8603 (Japan); Sekine, R. [Department of Chemistry, Faculty of Science, Shizuoka University, 836 Ohya, Shizuoka 422-8529 (Japan); Morinaga, M. [Department of Materials Science and Engineering, Graduate School of Engineering, Nagoya University, Chikusa-Ku, Nagoya 464-8603 (Japan)

    2007-10-31

    In situ Raman spectroscopy measurements have been performed during the decomposition of NaAlH{sub 4} in order to investigate the transition from the four-coordinated complex anion, [AlH{sub 4}]{sup -}, in NaAlH{sub 4} to the six-coordinated complex anion, [AlH{sub 6}]{sup 3-}, in Na{sub 3}AlH{sub 6}. Also, the local geometry and the Al-H vibrations are analyzed theoretically by the first-principle calculations of the electronic structures. It is found that the Raman sift at 1765 cm{sup -1} for the Al-H stretching vibration in NaAlH{sub 4} shifts towards the higher frequency side, 1801 cm{sup -1} upon melting. This Raman spectrum for the liquid phase recovers to the original position when it is cooled down to room temperature before Na{sub 3}AlH{sub 6} start to appear. The Raman peak around 1800 cm{sup -1} is still observed after the decomposition of NaAlH{sub 4} occurs to precipitate Na{sub 3}AlH{sub 6}. However, this peak does not recover to its original position by cooling, but still persists in the sample cooled down to room temperature. From these results, the intermediate transition state during the decomposition of NaAlH{sub 4} into Na{sub 3}AlH{sub 6} is discussed. In addition, it is shown from a series of calculation that the highest frequency of the Al-H vibration correlates with the shortest Al-H bond length in the MAlH{sub 4}-type and its derivative complex hydrides.

  2. 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.

  3. 23Na and 35/37Cl as NMR probes of growth and shape of sodium taurodeoxycholate micellar aggregates in the presence of NaCl.

    Science.gov (United States)

    Asaro, Fioretta; Feruglio, Luigi; Galantini, Luciano; Nardelli, Alessia

    2013-02-15

    The growth of the aggregates of the dihydroxylated bile salt sodium taurodeoxycholate (NaTDC) upon NaCl addition and the involvement of the counterion were investigated by NMR spectroscopy of monoatomic ionic species. (23)Na T(1) values from 0.015, 0.100, and 0.200 mol kg(-1) NaTDC solutions in D(2)O, at variable NaCl content, proved to be sensitive to the transition from primary to secondary aggregates, which occurs in the former sample, and to intermicellar interaction. Some (79)Br NMR measurements were performed on a 0.100 mol kg(-1) NaTDC sample added by NaBr in place of NaCl for comparison purposes. The (23)Na, (35)Cl, and (37)Cl double quantum filtered (DQF) patterns, from the 0.100 mol kg(-1) NaTDC sample, and (23)Na ones also from the 0.200 mol kg(-1) NaTDC one, in the presence of 0.750 mol kg(-1) NaCl, are a clear manifestation of motional anisotropy. Moreover, the DQF spectra of (23)Na and (37)Cl, which possess close quadrupole moments, display a striking similarity. The DQF lineshapes were simulated exploiting the Scilab environment to obtain an estimate of the residual quadrupole splitting magnitude. These results support the description of NaTDC micelles as cylindrical aggregates, strongly interacting at high ionic strengths, and capable of association with added electrolytes. Copyright © 2012 Elsevier Inc. All rights reserved.

  4. Robust high pressure stability and negative thermal expansion in sodium-rich antiperovskites Na3OBr and Na4OI2

    International Nuclear Information System (INIS)

    Wang, Yonggang; Wen, Ting; Park, Changyong; Kenney-Benson, Curtis; Pravica, Michael; Zhao, Yusheng; Yang, Wenge

    2016-01-01

    The structure stability under high pressure and thermal expansion behavior of Na 3 OBr and Na 4 OI 2 , two prototypes of alkali-metal-rich antiperovskites, were investigated by in situ synchrotron X-ray diffraction techniques under high pressure and low temperature. Both are soft materials with bulk modulus of 58.6 GPa and 52.0 GPa for Na 3 OBr and Na 4 OI 2 , respectively. The cubic Na 3 OBr structure and tetragonal Na 4 OI 2 with intergrowth K 2 NiF 4 structure are stable under high pressure up to 23 GPa. Although being a characteristic layered structure, Na 4 OI 2 exhibits nearly isotropic compressibility. Negative thermal expansion was observed at low temperature range (20–80 K) in both transition-metal-free antiperovskites for the first time. The robust high pressure structure stability was examined and confirmed by first-principles calculations among various possible polymorphisms qualitatively. The results provide in-depth understanding of the negative thermal expansion and robust crystal structure stability of these antiperovskite systems and their potential applications

  5. Thermoluminescence and F centers of manganese doped NaCl and NaCl-CKl crystals exposed to gamma radiation

    International Nuclear Information System (INIS)

    Somera, L.; Cruz Z, E.; Roman L, J.; Hernandez A, J. M.; Murrieta S, H.

    2015-10-01

    Alkali halides crystals doped with rare earths or transition metals have been widely studied due to the luminescence properties. In particular, NaCl and KCl single crystals present thermally stimulated luminescence (Tl) after gamma irradiation. The NaCl and the NaCl KCl mixed crystal doped with manganese (MnCl 2 ) impurity were grown by using the Czochralski method. The emission characteristic of Mn 2+ was observed at 543 nm. The crystals were exposed between 0.02 and 10 kGy gamma dose from 60 Co irradiator. Optical absorption at room temperature shows the peaked band at 452 nm corresponding to the manganese impurity. The F bands, was ascribed to the electron trapped in the anion vacancy in the lattice, were obtained at 452 nm and 455 nm belonging to NaCl:Mn and NaCl KCl:Mn, respectively. The F band increases as the doses increase and it was bleaching by the UV light at 470 nm. The glow curves of the samples show the first glow peak between 92-103 degrees C, while the second main peak was observed at 183 degrees C for the undoped NaCl and at 148 and 165 degrees C for the NaCl:Mn and NaCl-KCl:Mn, respectively. The main peak was slowly bleaching when the irradiated sample was illuminated with F (470 nm) light. Optical bleaching confirms that the F center has an important participation in the thermoluminescent response. The glow curves structure from the thermal bleaching suggests the participation of different kind of traps. Also, the kinetics parameters such as activation energy (E), frequency factor (s) and the kinetic order (b) were investigated. (Author)

  6. Thermoluminescence and F centers of manganese doped NaCl and NaCl-CKl crystals exposed to gamma radiation

    Energy Technology Data Exchange (ETDEWEB)

    Somera, L.; Cruz Z, E.; Roman L, J. [UNAM, Instituto de Ciencias Nucleares, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Hernandez A, J. M.; Murrieta S, H., E-mail: ecruz@nucleares.unam.mx [UNAM, Instituto de Fisica, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2015-10-15

    Alkali halides crystals doped with rare earths or transition metals have been widely studied due to the luminescence properties. In particular, NaCl and KCl single crystals present thermally stimulated luminescence (Tl) after gamma irradiation. The NaCl and the NaCl KCl mixed crystal doped with manganese (MnCl{sub 2}) impurity were grown by using the Czochralski method. The emission characteristic of Mn{sup 2+} was observed at 543 nm. The crystals were exposed between 0.02 and 10 kGy gamma dose from {sup 60}Co irradiator. Optical absorption at room temperature shows the peaked band at 452 nm corresponding to the manganese impurity. The F bands, was ascribed to the electron trapped in the anion vacancy in the lattice, were obtained at 452 nm and 455 nm belonging to NaCl:Mn and NaCl KCl:Mn, respectively. The F band increases as the doses increase and it was bleaching by the UV light at 470 nm. The glow curves of the samples show the first glow peak between 92-103 degrees C, while the second main peak was observed at 183 degrees C for the undoped NaCl and at 148 and 165 degrees C for the NaCl:Mn and NaCl-KCl:Mn, respectively. The main peak was slowly bleaching when the irradiated sample was illuminated with F (470 nm) light. Optical bleaching confirms that the F center has an important participation in the thermoluminescent response. The glow curves structure from the thermal bleaching suggests the participation of different kind of traps. Also, the kinetics parameters such as activation energy (E), frequency factor (s) and the kinetic order (b) were investigated. (Author)

  7. Occlusion of /sup 22/Na+ and /sup 86/Rb+ in membrane-bound and soluble protomeric alpha beta-units of Na,K-ATPase

    Energy Technology Data Exchange (ETDEWEB)

    Vilsen, B.; Andersen, J.P.; Petersen, J.; Jorgensen, P.L.

    1987-08-05

    In this work, we examined occlusion of /sup 22/Na+ and /sup 86/Rb+ in membranous and detergent-solubilized Na,K-ATPase from outer renal medulla. Optimum conditions for occlusion of /sup 22/Na+ were provided by formation of the phosphorylated complex from the beta,gamma-bidentate complex of chromium (III) with ATP (CrATP). Release of occluded cations occurred at equally slow rates in soluble and membrane-bound Na,K-ATPase. Values of /sup 22/Na+ occlusion as high as 11 nmol/mg of protein were measured, corresponding to 1.8-2.7 mol of Na+/mol of phosphorylated Na,K-ATPase as determined by /sup 32/P incorporation from (gamma-/sup 32/P)CrATP. Maximum capacity for phosphorylation from (gamma-/sup 32/P)CrATP was 6 nmol/mg of protein and equal to capacities for binding of (48V)vanadate and (/sup 3/H)ouabain. The stoichiometry for occlusion of Rb+ was close to 2 Rb+ ions/phosphorylation site. In an analytical ultracentrifuge, the soluble Na+- or Rb+-occluded complexes showed sedimentation velocities (S20,w = 6.8-7.4) consistent with monomeric alpha beta-units. The data show that soluble monomeric alpha beta-units of Na,K-ATPase can occlude Rb+ or Na+ with the same stoichiometry as the membrane-bound enzyme. The structural basis for occlusion of cations in Na,K-ATPase is suggested to be the formation of a cavity inside a monomeric alpha beta-unit constituting the minimum protein unit required for active Na,K-transport.

  8. Europlanet NA2 Science Networking

    Science.gov (United States)

    Harri, Ari-Matti; Szego, Karoly; Genzer, Maria; Schmidt, Walter; Krupp, Norbert; Lammer, Helmut; Kallio, Esa; Haukka, Harri

    2013-04-01

    Europlanet RI / NA2 Science Networking [1] focused on determining the major goals of current and future European planetary science, relating them to the Research Infrastructure that the Europlanet RI project [2] developed, and placing them in a more global context. NA2 also enhanced the ability of European planetary scientists to participate on the global scene with their own agenda-setting projects and ideas. The Networking Activity NA2 included five working groups, aimed at identifying key science issues and producing reference books on major science themes that will bridge the gap between the results of present and past missions and the scientific preparation of the future ones. Within the Europlanet RI project (2009-2012) the NA2 and NA2-WGs organized thematic workshops, an expert exchange program and training groups to improve the scientific impact of this Infrastructure. The principal tasks addressed by NA2 were: • Science activities in support to the optimal use of data from past and present space missions, involving the broad planetary science community beyond the "space club" • Science activities in support to the preparation of future planetary missions: Earth-based preparatory observations, laboratory studies, R&D on advanced instrumentation and exploration technologies for the future, theory and modeling etc. • Develop scientific activities, joint publications, dedicated meetings, tools and services, education activities, engaging the public and industries • Update science themes and addressing the two main scientific objectives • Prepare and support workshops of the International Space Science Institute (ISSI) in Bern and • Support Trans National Activities (TNAs), Joined Research Activities (JRAs) and the Integrated and Distributed Information Service (IDIS) of the Europlanet project These tasks were achieved by WG workshops organized by the NA2 working groups, by ISSI workshops and by an Expert Exchange Program. There were 17 official WG

  9. NA61/SHINE ion program

    CERN Document Server

    Mackowiak, Maja

    2010-01-01

    The Super Proton Synchrotron (SPS) at CERN covers one of the most interesting regions of the phase diagram (T - \\mu_{B}) of strongly interacting matter. The study of central Pb+Pb collisions by NA49 indicate that the threshold for deconfinement is reached already at the low SPS energies. Theoretical considerations predict a critical point of strongly interacting matter at energies accessible at the SPS. The NA61/SHINE experiment, a successor of the NA49 project, will study hadron production in p+p, p+A, h+A, and A+A reactions at various energies. The broad physics program includes the investigation of the properties of strongly interacting matter, as well as precision measurements of hadron spectra for the T2K neutrino experiment and for the Pierre Auger Observatory and KASCADE cosmic-ray projects. The main physics goals of the NA61/SHINE ion program are to study the properties of the onset of deconfinement at low SPS energies and to find signatures of the critical point of strongly interacting matter. To ach...

  10. Armas na escola: que fazer?

    Directory of Open Access Journals (Sweden)

    Raymundo de Lima

    2010-09-01

    Full Text Available

    Um aluno portava um revólver na sala de aula de uma escola de Maringá (O Diário, 30/07/2010. Ele pegou arma do pai, sem que este soubesse, para se proteger de garotos que o intimidavam. Trata-se de um caso isolado ou é hora de a escola tomar medidas preventivas? Semanas antes, tiros foram disparados dentro de uma faculdade da mesma cidade. O autor dos disparos está preso, e a faculdade tenta apagar as marcas com publicidade positiva na Tv. Em Campo Mourão, cidade a cerca de uma hora de Maringá, duas meninas foram mortas e enterradas na escola.

  11. Isotope separation of 22Na and 24Na with using light induced drift effect

    International Nuclear Information System (INIS)

    Hradecny, C.; Tethal, T.; Ermolaev, I.M.; Zemlyanoj, S.G.; Zuzaan, P.

    1993-01-01

    The LIDIS (Light Drift Isotope Separation) separator without a gas flow is discussed. It is shown, that atomization degree of the separated isotopes limited real separation coefficient. The better buffer gas purification allowed to increase the experimental separation factor of 22 Na and 24 Na isotopes up to 25. The new experimental set up allow to increase the separation efficiency up to 50%. 12 refs.; 5 figs

  12. MOBILNO POSLOVANJE NA PRIMERU UPORABE MICROSOFT DYNAMICS CRM

    OpenAIRE

    Duh, Tamara

    2016-01-01

    Hitro razvijajoči se svet nas spodbuja k hitremu reagiranju na novosti, ki se pojavljajo na trgu. Prav zaradi tega je danes zelo pomembno upravljati z mobilnimi napravami, da se lahko hitro in brez težav soočimo z morebitnimi težavami oz. zagatami. Prav iz tega razloga je mobilno poslovanje ena izmed inovativnih rešitev, ki ljudem omogoča seznanjenost z informacijami na vsakem koraku in omogoča hiter odziv na spremembe. Prav ta rešitev omogoča podjetjem, da so konkurenčna in hkrati lahko hitr...

  13. Usando a antimatéria na medicina moderna

    OpenAIRE

    Machado,A.C.B.; Pleitez,V.; Tijero,M.C.

    2006-01-01

    Neste artigo, fazemos uma breve exposição de como um dos conceitos fundamentais da física moderna, a existência de antimatéria, tem aplicação na medicina, na chamada tomografia por emissão de pósitrons (PET na sigla em inglês). Ela consiste na produção de imagens tomográficas digitais do organismo que são obtidas pela detecção da radiação produzida na aniquilação do pósitron com o elétron.

  14. 43. Calmodulin regulating calcium sensitivity of Na channels

    Directory of Open Access Journals (Sweden)

    R. Vegiraju

    2016-07-01

    Full Text Available By extrapolating information from existing research and observing previous assumptions regarding the structure of the Na Channel, this experiment was conducted under the hypothesis that the Na Channel is in part regulated by the calmodulin protein, as a result proving calcium sensitivity of the Na Channel. Furthermore, we assume that there is a one to one stoichiometry between the Na Channel and the Calmodulin. There has been extensive research into the functionality and structure of sodium ion channels (Na channels, as several diseases are associated with the lack of regulation of sodium ions, that is caused by the disfunction of these Na channels. However, one highly controversial matter in the field is the importance of the protein calmodulin (CaM and calcium in Na channel function. Calmodulin is a protein that is well known for its role as a calcium binding messenger protein, and that association is believed to play an indirect role in regulating the Na channel through the Na channel’s supposed calcium sensitivity. While there are proponents for both sides, there has been relatively little research that provides strong evidence for either case. In this experiment, the effect of calmodulin on NaV 1.5 is tested by preparing a set of cardiac cells (of the human specie with the NaV 1.5 C-Termini and CaM protein, which were then to be placed in solutions with varying concentrations of calcium. We took special care to test multiple concentrations of calcium, as previous studies have tested very low concentrations, with Manu Ben-Johny’s team from the John Hopkins laboratory in particular testing up to a meager 50 micromolar, despite producing a well-respected paper (By comparison, the average Na channel can naturally sustain a concentration of almost 1-2 millimolar and on some occasions, reaching even higher concentrations. After using light scattering and observing the signals given off by the calcium interacting with these Nav1.5/Ca

  15. In vivo PTH provokes apical NHE3 and NaPi2 redistribution and Na-K-ATPase inhibition

    DEFF Research Database (Denmark)

    Zhang, Y; Norian, J M; Magyar, C E

    1999-01-01

    and to determine whether the same cellular signals drive the changes in apical and basolateral transporters. PTH-(1-34) (20 U), which couples to adenylate cyclase (AC), phospholipase C (PLC), and phospholipase A2 (PLA2), or [Nle8,18,Tyr34]PTH-(3-34) (10 U), which couples to PLC and PLA2 but not AC, were given....../diuresis and NHE3 and NaPi2 internalization, and that Na-K-ATPase inhibition is not secondary to depressed apical Na+ transport....

  16. Aspectos valorizados por porfissionais de enfermagem na higiene pessoal e na higiene corporal do paciente

    Directory of Open Access Journals (Sweden)

    Elóide André Oliveira

    2003-10-01

    Full Text Available Survey descritivo, com o qual se objetivou identificar que aspectos da higiene corporal são valorizados pelos componentes da equipe de enfermagem, na higiene corporal pessoal e na higiene corporal do paciente. A pesquisa foi desenvolvida em oito instituições públicas de saúde e a amostra foi composta por 126 profissionais de enfermagem, correspondendo a 12,8% do total de 986 componentes das equipes de enfermagem destas instituições. Na higiene corporal pessoal, chamou a atenção o fato de que os cuidados com as unhas e com os cabelos tenham suplantado, no número de citações dos profissionais de enfermagem, aspectos básicos como o cuidado com as mãos. Na higiene corporal do paciente, o banho foi o aspecto considerado mais importante pelas três categorias profissionais; a higiene oral, pelas(os enfermeiras(os e auxiliares de enfermagem; e as unhas, pelas(os enfermeiras(os e técnicas(os de enfermagem.

  17. Modulation of contraction by intracellular Na+ via Na(+)-Ca2+ exchange in single shark (Squalus acanthias) ventricular myocytes.

    Science.gov (United States)

    Näbauer, M; Morad, M

    1992-01-01

    1. The effect of direct alteration of intracellular Na+ concentration on contractile properties of whole-cell clamped shark ventricular myocytes was studied using an array of 256 photodiodes to monitor the length of the isolated myocytes. 2. In myocytes dialysed with Na(+)-free solution, the voltage dependence of Ca2+ current (ICa) and contraction were similar and bell shaped. Contractions activated at all voltages were completely suppressed by nifedipine (5 microM), and failed to show significant tonic components, suggesting dependence of the contraction on Ca2+ influx through the L-type Ca2+ channel. 3. In myocytes dialysed with 60 mM Na+, a ICa-dependent and a ICa-independent component of contraction could be identified. The Ca2+ current-dependent component was prominent in voltages between -30 to +10 mV. The ICa-independent contractions were maintained for the duration of depolarization, increased with increasing depolarization between +10 to +100 mV, and were insensitive to nifedipine. 4. In such myocytes, repolarization produced slowly decaying inward tail currents closely related to the time course of relaxation and the degree of shortening prior to repolarization. 5. With 60 mM Na+ in the pipette solution, positive clamp potentials activated decaying outward currents which correlated to the size of contraction. These outward currents appeared to be generated by the Na(+)-Ca(2+)-exchanger since they depended on the presence of intracellular Na+, and were neither suppressed by nifedipine nor by K+ channel blockers. 6. The results suggest that in shark (Squalus acanthias) ventricular myocytes, which lack functionally relevant Ca2+ release pools, both Ca2+ channel and the Na(+)-Ca2+ exchanger deliver sufficient Ca2+ to activate contraction, though the effectiveness of the latter mechanism was highly dependent on the [Na+]i. PMID:1338467

  18. KANDUNGAN NATRIUM (Na DAN GARAM (NaCl DALAM IKAN ASIN KERING MENTAH DAN GORENG DI PASAR ANYAR BOGOR

    Directory of Open Access Journals (Sweden)

    Heru Yuniati

    2012-11-01

    Full Text Available Telah dilakukan penelitian untuk mengetahui kandungan natrium (Na dan garam (NaCl dalam 10 jenis ikan asin kering yang beredar di Pasar Anyar Bogor. Analisis natrium dilakukan terhadap ikan asin mentah, setelah dicuci, dan setelah digoreng dengan menggunakan flamefometer. Analisis garam dilakukan dengan titrasi argentometri terhadap ikan asin mentah. Hasil analisis menunjukkan, kandungan Na dan garam dalam ikan asin sangat beragam besarnya berturut-turut berkisar antara 0,3-8,1% dan 5,7-21,2%. Ikan asin yang mempunyai kadar Na dan garam tinggi adalah ikan sepat, peda putih dan gabus. Jumlah air dalam ikan asin juga bervariasi, berkisar antara 10,3-46,8%. pencucian dan penggorengan dapat menurunkan kadar garam ataupun natrium sebesar 37,4%.

  19. Aprendizagem como/na prática

    Directory of Open Access Journals (Sweden)

    Jean Lave

    2015-12-01

    Full Text Available ResumoEste artigo considera como o estudo da cultura e da aprendizagem pode ser de particular relevância para o campo da antropologia sociocultural em geral. O termo mais importante na expressão “cultura & aprendizagem” talvez seja o logograma “&” – ou seja, coloca-se a questão sobre o que conecta cultura e aprendizagem, perguntando-se como esses termos estão relacionados. Como devemos compreender cultura e aprendizagem como instâncias produtoras delas próprias, e uma da outra, na prática? Recalibrando em termos relacionais, podemos dizer que não é possível abordar a “aprendizagem” ou “cultura e aprendizagem” sem o seu emaranhamento na vida político-econômica, nas lutas e disputas históricas, em suas coerências e incoerências, e na produção relacional e histórica da vida cotidiana. Através das lentes da teoria da prática social, os estudos etnográficos sobre aprendizagem na prática oferecem diferentes entendimentos sobre como certa vida e certas disputas e incoerências são produzidas.

  20. Metodologija analize stroškov in koristi za investicije v prometno infrastrukturo na osnovi Poročila vplivov na okolje

    OpenAIRE

    Podvornik, Nina

    2016-01-01

    Povečane potrebe po prometnem omrežju vodijo k dodatnim prometnim investicijam, ki so ne glede na njihov obseg, postavitev v prostor ter učinkovitost pomemben dejavnik gospodarskega razvoja. Investicije v prometno infrastrukturo lahko na sam razvoj vplivajo pozitivno (dvig gospodarske rasti, kakovost življenja, dostopnost idr.) in tudi negativno (različni vplivi na okolje). Ker so prometne investicije zelo obsežne, je vsestranska ocena le-teh ključnega pomena pri samem prometnem načrtovanju v...

  1. Agmag Igbo dka Ngwar n'kwalite Ezi Nchekwa na Nkwsiike haobodo

    African Journals Online (AJOL)

    Ka Najira nwerechara onwe ya n'af 1960, olileanya tt mamala ya b na ihe ga-adz mma. Mana ka oge na-aga, a chptara na ihe na-akawanye nj. Usoro chch d iche iche daptara. Nd am na nd nkt achala mana nd gara n'ihu na-akawanye nj. O bu ihe doro anya na chch ha b nke nchgbu na fnfju akpa. N'agbanyegh na ...

  2. Regulation of Epithelial Sodium Transport via Epithelial Na+ Channel

    Science.gov (United States)

    Marunaka, Yoshinori; Niisato, Naomi; Taruno, Akiyuki; Ohta, Mariko; Miyazaki, Hiroaki; Hosogi, Shigekuni; Nakajima, Ken-ichi; Kusuzaki, Katsuyuki; Ashihara, Eishi; Nishio, Kyosuke; Iwasaki, Yoshinobu; Nakahari, Takashi; Kubota, Takahiro

    2011-01-01

    Renal epithelial Na+ transport plays an important role in homeostasis of our body fluid content and blood pressure. Further, the Na+ transport in alveolar epithelial cells essentially controls the amount of alveolar fluid that should be kept at an appropriate level for normal gas exchange. The epithelial Na+ transport is generally mediated through two steps: (1) the entry step of Na+ via epithelial Na+ channel (ENaC) at the apical membrane and (2) the extrusion step of Na+ via the Na+, K+-ATPase at the basolateral membrane. In general, the Na+ entry via ENaC is the rate-limiting step. Therefore, the regulation of ENaC plays an essential role in control of blood pressure and normal gas exchange. In this paper, we discuss two major factors in ENaC regulation: (1) activity of individual ENaC and (2) number of ENaC located at the apical membrane. PMID:22028593

  3. Na+,K+ pumpen vedbliver at overraske

    DEFF Research Database (Denmark)

    Vilsen, Bente

    2008-01-01

    This article provides an overview of news about the Na+,K+ pump, an indispensable enzyme whose protein structure has been described in a recent article in Nature, 50 years after its discovery. In combination with mutational analysis, the structure reveals the binding pocket for the K+ ions...... and the regulation of Na+ transport by a strategically located C-terminus of the protein. Focus is also on the pathophysiology of two neurological disorders, familial hemiplegic migraine and rapid-onset dystonia-parkinsonism, recently shown to be caused by mutations in the Na+,K+-ATPase. Udgivelsesdato: may 19...

  4. Risbjerg: Historisk stemmeskred med NA

    DEFF Research Database (Denmark)

    Thomsen, Søren Risbjerg

    2007-01-01

    ANALYSE: NA flytter 12,3 pct. af stemmerne i majs meningsmålinger - historisk mange vælgere på en måned, skriver professor Risbjerg. Udgivelsesdato: 3. juni 2007......ANALYSE: NA flytter 12,3 pct. af stemmerne i majs meningsmålinger - historisk mange vælgere på en måned, skriver professor Risbjerg. Udgivelsesdato: 3. juni 2007...

  5. Dissolution of targets for the production of Mo-99: Part 1. Influence of NaOH concentration and the addition of NaNO{sub 3} and NaNO{sub 2} on the dissolution time

    Energy Technology Data Exchange (ETDEWEB)

    Camilo, Ruth L.; Araujo, Izilda da C.; Mindrisz, Ana C.; Forbicini, Christina A.L.G. de O., E-mail: rcamilo@ipen.br, E-mail: icaraujo@ipen.br, E-mail: acmindri@ipen.br, E-mail: cforbici@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN/SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Faced with global crisis in the production of radioisotope {sup 99}Mo, which product of decay, {sup 99}mTc, is the tracer element most often used in nuclear medicine and accounts for about 80% of all diagnostic procedures in vivo, since September 2008 Brazil is developing the project called Brazilian Multipurpose Reactor (RMB). Within the Brazilian Nuclear Program (PNB) the construction of the RMB, is seen as a long term solution to meet all domestic demand relative to the supply of radioisotopes and radiopharmaceuticals. In the process to be studied to obtain {sup 99}Mo from irradiated UA1{sub x}-A1 LEU targets employing alkaline dissolution, processing time should be minimized, considering the short half life of {sup 99}Mo and {sup 99}mTc, about 66 h and 6 h, respectively. That makes dissolution time a significant factor in the development of the process. This paper presents the results of alkaline dissolution of scraps of Al, used to simulate the dissolution process of UA1{sub x}-A1 targets. Al corresponds to about 79% of the total weight of the UA1{sub x}-A1 target. The effect of NaOH concentration on dissolution time for the interval of 1 to 3.5 mol.L-1 was studied, keeping the molar ratio in 1Al:2.16NaOH and the initial temperature of 88 degree C. The influence of reagent composition over dissolution time was studied using three different solutions: a) 3 mol.L{sup -1} NaOH, b) 3 mol.L{sup -1} NaOH/NaNO{sub 3} and c) 3 mol.L{sup -1} NaOH/NaNO{sub 2}, keeping the same molar ratio and temperature. The results showed that the dissolution time decreases with increasing NaOH concentration and the addition of NaNO{sub 3} or NaNO{sub 2} in the NaOH solution reduces both dissolution time and volume of gases released. (author)

  6. Crystal Structure of Na3MoCl6

    Directory of Open Access Journals (Sweden)

    Martin Beran

    2011-07-01

    Full Text Available The ternary chloride Na3MoCl6 is obtained as red crystals from a disproportionation reaction of molybdenum dichloride, {Mo6}Cl12, in an acidic NaCl/AlCl3 melt at 350 °C. The crystal structure (trigonal, P-31c, a = 687.1(1, c = 1225.3(2 pm, Z = 2, V = 501,0(1 106 pm3 is that of Na3CrCl6: within a hexagonal closest-packing of chloride ions two thirds of the octahedral voids are filled between the AB double layers with Na+/Mo3+, and between the BA layers with Na+.

  7. Diffusion of calcium in pure and doped NaCl; Diffusion du calcium dans NaCl pur et dope

    Energy Technology Data Exchange (ETDEWEB)

    Slifkin, L; Brebec, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    We have determined, by diffusion experiments of Ca in pure and doped NaCl, the activation energy for the calcium jumps and the binding energy between calcium ion and vacancy. (authors) [French] Nous avons determine, par des mesures de diffusion du Ca dans NaCl pur et NaCl dope avec CaCl{sub 2}, l'energie d'activation relative aux sauts du calcium et l'energie de liaison lacune-calcium. (auteurs)

  8. Wizerunek ateisty i jego miejsce na konfesyjnej mapie świata na Śląsku Cieszyńskim

    Directory of Open Access Journals (Sweden)

    Zbigniew Greń

    2017-12-01

    Full Text Available The image of the atheist and his place on the confessional map of the world in Cieszyn Silesia The aim of this article is to create an image of the atheist based on historical and contemporary sources. The history of the concept of the atheist is described on the basis of the regional press, the contemporary picture of the concept – on the basis of the results of a questionnaire and discussions on religious topics on regional websites. The analysis showed that the concept of the atheist is treated as a term equivalent to the terms of members of different churches. The research shows not only the image of the atheist, but also its place in the system of perception of religious differences.   Wizerunek ateisty i jego miejsce na konfesyjnej mapie świata na Śląsku Cieszyńskim Celem niniejszego artykułu jest stworzenie obrazu ateisty na podstawie źródeł historycznych i współczesnych. Historia pojęcia ateisty została opisana na podstawie prasy regionalnej, współczesny obraz – na podstawie wyników ankiet i dyskusji na tematy religijne na regionalnych stronach internetowych. Analiza wykazała, że pojęcie ateisty jest traktowane jako pojęcie równorzędne z określeniami członków różnych Kościołów. W wyniku badań przedstawiono nie tylko wizerunek ateisty, lecz także jego miejsce w systemie postrzegania różnic wyznaniowych.

  9. Mabadiliko Ya Kifonolojia Na Kimofolojia Wakati Wa Utohozi Wa ...

    African Journals Online (AJOL)

    Mwingiliano wa lugha ya Kiswahili na Kiarabu una historia ndefu kidogo. Inasemekana Waarabu walianza muwasala na 'Waswahili' tangu karne ya kwanza (BK) (Polome 1967:9). Kutokana na muwasala huo wa muda mrefu, lugha hizi mbili (Kiarabu na Kiswahili) zimeathiriana sana. Lakini kuna maoni kwamba Kiarabu ...

  10. Aqueous partial molar heat capacities and volumes for NaReO4 and NaTcO4

    International Nuclear Information System (INIS)

    Lemire, R.J.; Saluja, P.P.S.; Campbell, A.B.

    1989-01-01

    As part of the Canadian Nuclear Fuel Waste Management Program, data are required to model the equilibrium thermodynamic behavior of key radionuclides at temperatures above 25 degree C. A flow microcalorimeter/densimeter system has been commissioned to measure heat capacities and densities of solutions containing radioactive species. Measurements for solutions of aqueous NaReO 4 (a common analogue for NaTcO 4 ) were made at seven temperatures (15 to 100 degree C) over the concentration range 0.05 to 0.2 mol·kg -1 . Subsequently, measurements were made for NaTcO 4 solutions under similar conditions. The heat capacity and density data are analyzed using Pitzer's ion-interaction model, and values of the NaReO 4 partial molar heat capacities are compared to literature values based on integral heats of solution. The agreement between the two sets of NaReO 4 data is good below 75 degree C, but only fair at the higher temperatures. Values of the partial molar volumes have also been derived. The uncertainties introduced by using thermodynamic data for ReO 4 - , in the absence of data for TcO 4 - , are discussed

  11. Effects of dietary Na+ deprivation on epithelial Na+ channel (ENaC, BDNF, and TrkB mRNA expression in the rat tongue

    Directory of Open Access Journals (Sweden)

    Stähler Frauke

    2009-03-01

    Full Text Available Abstract Background In rodents, dietary Na+ deprivation reduces gustatory responses of primary taste fibers and central taste neurons to lingual Na+ stimulation. However, in the rat taste bud cells Na+ deprivation increases the number of amiloride sensitive epithelial Na+ channels (ENaC, which are considered as the "receptor" of the Na+ component of salt taste. To explore the mechanisms, the expression of the three ENaC subunits (α, β and γ in taste buds were observed from rats fed with diets containing either 0.03% (Na+ deprivation or 1% (control NaCl for 15 days, by using in situ hybridization and real-time quantitative RT-PCR (qRT-PCR. Since BDNF/TrkB signaling is involved in the neural innervation of taste buds, the effects of Na+ deprivation on BDNF and its receptor TrkB expression in the rat taste buds were also examined. Results In situ hybridization analysis showed that all three ENaC subunit mRNAs were found in the rat fungiform taste buds and lingual epithelia, but in the vallate and foliate taste buds, only α ENaC mRNA was easily detected, while β and γ ENaC mRNAs were much less than those in the fungiform taste buds. Between control and low Na+ fed animals, the numbers of taste bud cells expressing α, β and γ ENaC subunits were not significantly different in the fungiform, vallate and foliate taste buds, respectively. Similarly, qRT-PCR also indicated that Na+ deprivation had no effect on any ENaC subunit expression in the three types of taste buds. However, Na+ deprivation reduced BDNF mRNA expression by 50% in the fungiform taste buds, but not in the vallate and foliate taste buds. The expression of TrkB was not different between control and Na+ deprived rats, irrespective of the taste papillae type. Conclusion The findings demonstrate that dietary Na+ deprivation does not change ENaC mRNA expression in rat taste buds, but reduces BDNF mRNA expression in the fungiform taste buds. Given the roles of BDNF in survival of

  12. Hydrogen production by sodium borohydride in NaOH aqueous solution

    Science.gov (United States)

    Wang, Q.; Zhang, L. F.; Zhao, Z. G.

    2018-01-01

    The kinetics of hydrolysis reaction of NaBH4 in NaOH aqueous solution is studied. The influence of pH of the NaOH aqueous solution on the rate of hydrogen production and the hydrogen production efficiency are studied for the hydrolysis reaction of NaBH4. The results show that the activation energy of hydrolysis reaction of NaBH4 increased with the increase of the initial pH of NaOH aqueous solution.With the increasing of the initial pH of NaOH aqueous solution, the rate of hydrogen production and hydrogen production efficiency of NaBH4 hydrolysis decrease.

  13. Altered Regulation of type 3 Na+/H+ exchanger, type 1 Na+/HCO3- cotransporter, and Na+,K+-ATPase in the Kidney of Rats with Experimental Rhabdomyolysis

    Science.gov (United States)

    Ma, Seong Kwon; Bae, Eun Hui; Lee, JongUn; Kim, Sun Young; Kim, Sung Zoo; Choi, Ki Chul

    2007-01-01

    Metabolic acidosis was shown to correlate with deterioration of renal function in patients with rhabdomyolysis. The present study was aimed to investigate whether the changes of type 3 Na+/H+ exchanger (NHE3), type 1 Na+/HCO3- cotransporter (NBC1), and Na+,K+-ATPase α1 subunit may play a role in the pathogenesis of metabolic acidosis in glycerol-induced experimental rhabdomyolysis. Male Sprague-Dawley rats were deprived of fluid intake for 24 hours, and then were injected with 50% glycerol in normal saline (10 mL/kg, intramuscularly). At 24 hours after the glycerol injection, rats were sacrificed by decapitation. Control rats were injected with normal saline. The protein expression of NHE3, NBC1 and Na+,K+-ATPase α1 subunit was determined in the cortex of the kidney by immunoblotting and immunohistochemistry. Following the treatment of glycerol, creatinine clearance was significantly decreased, and high anion gap metabolic acidosis developed. In the experimental group, the expression of Na+,K+-ATPase α1 subunit was significantly decreased in the cortex of the kidney. On the contrary, the expression of NHE3 and NBC1 was significantly increased. Immunohistochemical analyses confirmed the immunoblotting data. In conclusion, the coordinate up-regulation of NHE3 and NBC1 may play an adaptive role against the metabolic acidosis in glycerol-induced rhabdomyolysis. PMID:24459502

  14. K+ congeners that do not compromise Na+ activation of the Na+,K+-ATPase

    DEFF Research Database (Denmark)

    Mahmmoud, Yasser A; Kopec, Wojciech; Khandelia, Himanshu

    2015-01-01

    The Na(+),K(+)-ATPase is essential for ionic homeostasis in animal cells. The dephosphoenzyme contains Na(+) selective inward facing sites, whereas the phosphoenzyme contains K(+) selective outward facing sites. Under normal physiological conditions, K(+) inhibits cytoplasmic Na(+) activation...

  15. Kupokelewa Zaidi Kwa Simu Ya Mkononi Kuliko Kompyuta Na ...

    African Journals Online (AJOL)

    Mtandao wa tovuti ni nyenzo ya msingi katika maendeleo ya uwanja wa mawasiliano unaounganisha watu na jamii mbalimbali katika ulimwengu wa leo unaotandawaa. Katika “ulimwengu wa kwanza na wa pili”, yaani mabara ya Amerika, Uropa na Asia, maendeleo na mapinduzi makubwa katika uwanja wa teknolojia ya ...

  16. 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.

  17. Silicene for Na-ion battery applications

    KAUST Repository

    Zhu, Jiajie; Schwingenschlö gl, Udo

    2016-01-01

    Na-ion batteries are promising candidates to replace Li-ion batteries in large scale applications because of the advantages in natural abundance and cost of Na. Silicene has potential as the anode in Li-ion batteries but so far has not received

  18. Coulomb excitation of radioactive 20, 21Na

    Science.gov (United States)

    Schumaker, M. A.; Cline, D.; Hackman, G.; Pearson, C.; Svensson, C. E.; Wu, C. Y.; Andreyev, A.; Austin, R. A. E.; Ball, G. C.; Bandyopadhyay, D.; Becker, J. A.; Boston, A. J.; Boston, H. C.; Buchmann, L.; Churchman, R.; Cifarelli, F.; Cooper, R. J.; Cross, D. S.; Dashdorj, D.; Demand, G. A.; Dimmock, M. R.; Drake, T. E.; Finlay, P.; Gallant, A. T.; Garrett, P. E.; Green, K. L.; Grint, A. N.; Grinyer, G. F.; Harkness, L. J.; Hayes, A. B.; Kanungo, R.; Lisetskiy, A. F.; Leach, K. G.; Lee, G.; Maharaj, R.; Martin, J.-P.; Moisan, F.; Morton, A. C.; Mythili, S.; Nelson, L.; Newman, O.; Nolan, P. J.; Orce, J. N.; Padilla-Rodal, E.; Phillips, A. A.; Porter-Peden, M.; Ressler, J. J.; Roy, R.; Ruiz, C.; Sarazin, F.; Scraggs, D. P.; Waddington, J. C.; Wan, J. M.; Whitbeck, A.; Williams, S. J.; Wong, J.

    2009-12-01

    The low-energy structures of the radioactive nuclei 20, 21Na have been examined using Coulomb excitation at the TRIUMF-ISAC radioactive ion beam facility. Beams of ˜ 5×106 ions/s were accelerated to 1.7MeV/A and Coulomb excited in a 0.5mg/cm^2 natTi target. Two TIGRESS HPGe clover detectors perpendicular to the beam axis were used for γ -ray detection, while scattered nuclei were observed by the Si detector BAMBINO. For 21Na , Coulomb excitation from the 3/2+ ground state to the first excited 5/2+ state was observed, while for 20Na , Coulomb excitation was observed from the 2+ ground state to the first excited 3+ and 4+ states. For both beams, B ( λ L) values were determined using the 2+ rightarrow 0+ de-excitation in 48Ti as a reference. The resulting B( E2) ↓ value for 21Na is 137±9 e^2fm^4, while the resulting B( λ L) ↓ values for 20Na are 55±6 e^2fm^4 for the 3+ rightarrow 2+ , 35.7±5.7 e^2 fm^4 for the 4+ rightarrow 2+ , and 0.154±0.030 μ_ N^2 for the 4+ rightarrow 3+ transitions. This analysis significantly improves the measurement of the 21Na B( E2) value, and provides the first experimental determination of B( λ L) values for the proton dripline nucleus 20Na .-1

  19. Detailed investigation of Na2.24FePO4CO3 as a cathode material for Na-ion batteries

    Science.gov (United States)

    Huang, Weifeng; Zhou, Jing; Li, Biao; Ma, Jin; Tao, Shi; Xia, Dingguo; Chu, Wangsheng; Wu, Ziyu

    2014-01-01

    Na-ion batteries are gaining an increased recognition as the next generation low cost energy storage devices. Here, we present a characterization of Na3FePO4CO3 nanoplates as a novel cathode material for sodium ion batteries. First-principles calculations reveal that there are two paths for Na ion migration along b and c axis. In-situ and ex-situ Fe K-edge X-ray absorption near edge structure (XANES) point out that in Na3FePO4CO3 both Fe2+/Fe3+ and Fe3+/Fe4+ redox couples are electrochemically active, suggesting also the existence of a two-electron intercalation reaction. Ex-situ X-ray powder diffraction data demonstrates that the crystalline structure of Na3FePO4CO3 remains stable during the charging/discharging process within the range 2.0–4.55 V. PMID:24595232

  20. Artesanato na terceira idade: um estudo na cidade de Sinop no ano de 2011

    Directory of Open Access Journals (Sweden)

    Rosane Marlene Weber

    2015-04-01

    Full Text Available Essa pesquisa tem como objetivo mostrar a importância do artesanato na Terceira Idade como atividade educacional e de autonomia para os idosos. Por existir uma preocupação com a qualidade de vida da Terceira Idade e sua autonomia, nesta fase que muitos acabam ficando dependentes dos membros da família, espera-se encontrar através da arte uma motivação e uma forma de demonstrar a autoria por meio do fazer, criar e recriar com o artesanato. Aprender e ensinar são um processo contínuo na vida do ser humano, independente da idade, para Paulo Freire precisamos ter consciência de que somos inacabados, e sendo conscientes de nossa inconclusão, devemos viver num permanente movimento de busca. Essa é uma das causas pelas quais será pesquisada a prática formativa/educacional por meio do artesanato na Terceira Idade. Os motivos que levaram a escolha desta pesquisa com o artesanato na Terceira Idade é o fato de ter vivido uma experiência de trabalho na ala geriátrica de um hospital. Já o artesanato é a arte que fascina, e acreditamos que sempre há tempo para recomeçar, para descobrir algo que possa trazer qualidade para nossa vida. Devido ao crescimento cada vez maior da expectativa de vida em nosso país, cria-se uma preocupação com a qualidade de vida das pessoas da Terceira Idade. Em relação aos aspectos educacionais e culturais, esta pesquisa deseja compreender como o artesanato pode trazer motivação para as pessoas da Terceira Idade como forma de autoria e autonomia, nesta fase da vida, na cidade de Sinop, e quais os motivos que os levam a realizar esse tipo de atividade. Para investigação teórica desta pesquisa do Artesanato na Terceira Idade: um estudo na cidade de Sinop em 2011 usaremos bibliografia de vários autores, mas em especial os que dedicam seus estudos a esta faixa etária, como a coleção de Vivaidade, que tem como organizadora principal Anita Liberalesso Neri. Os autores desta coleção nos trazem a reflex

  1. Biphasic voltage-dependent inactivation of human NaV 1.3, 1.6 and 1.7 Na+ channels expressed in rodent insulin-secreting cells.

    Science.gov (United States)

    Godazgar, Mahdieh; Zhang, Quan; Chibalina, Margarita V; Rorsman, Patrik

    2018-05-01

    Na + current inactivation is biphasic in insulin-secreting cells, proceeding with two voltage dependences that are half-maximal at ∼-100 mV and -60 mV. Inactivation of voltage-gated Na + (Na V ) channels occurs at ∼30 mV more negative voltages in insulin-secreting Ins1 and primary β-cells than in HEK, CHO or glucagon-secreting αTC1-6 cells. The difference in inactivation between Ins1 and non-β-cells persists in the inside-out patch configuration, discounting an involvement of a diffusible factor. In Ins1 cells and primary β-cells, but not in HEK cells, inactivation of a single Na V subtype is biphasic and follows two voltage dependences separated by 30-40 mV. We propose that Na V channels adopt different inactivation behaviours depending on the local membrane environment. Pancreatic β-cells are equipped with voltage-gated Na + channels that undergo biphasic voltage-dependent steady-state inactivation. A small Na + current component (10-15%) inactivates over physiological membrane potentials and contributes to action potential firing. However, the major Na + channel component is completely inactivated at -90 to -80 mV and is therefore inactive in the β-cell. It has been proposed that the biphasic inactivation reflects the contribution of different Na V α-subunits. We tested this possibility by expression of TTX-resistant variants of the Na V subunits found in β-cells (Na V 1.3, Na V 1.6 and Na V 1.7) in insulin-secreting Ins1 cells and in non-β-cells (including HEK and CHO cells). We found that all Na V subunits inactivated at 20-30 mV more negative membrane potentials in Ins1 cells than in HEK or CHO cells. The more negative inactivation in Ins1 cells does not involve a diffusible intracellular factor because the difference between Ins1 and CHO persisted after excision of the membrane. Na V 1.7 inactivated at 15--20 mV more negative membrane potentials than Na V 1.3 and Na V 1.6 in Ins1 cells but this small difference is insufficient to solely

  2. A neural network potential energy surface for the NaH2 system and dynamics studies on the H(2S) + NaH(X1Σ+) → Na(2S) + H2(X1Σg+) reaction.

    Science.gov (United States)

    Wang, Shufen; Yuan, Jiuchuang; Li, Huixing; Chen, Maodu

    2017-08-02

    In order to study the dynamics of the reaction H( 2 S) + NaH(X 1 Σ + ) → Na( 2 S) + H 2 (X 1 Σ g + ), a new potential energy surface (PES) for the ground state of the NaH 2 system is constructed based on 35 730 ab initio energy points. Using basis sets of quadruple zeta quality, multireference configuration interaction calculations with Davidson correction were carried out to obtain the ab initio energy points. The neural network method is used to fit the PES, and the root mean square error is very small (0.00639 eV). The bond lengths, dissociation energies, zero-point energies and spectroscopic constants of H 2 (X 1 Σ g + ) and NaH(X 1 Σ + ) obtained on the new NaH 2 PES are in good agreement with the experiment data. On the new PES, the reactant coordinate-based time-dependent wave packet method is applied to study the reaction dynamics of H( 2 S) + NaH(X 1 Σ + ) → Na( 2 S) + H 2 (X 1 Σ g + ), and the reaction probabilities, integral cross-sections (ICSs) and differential cross-sections (DCSs) are obtained. There is no threshold in the reaction due to the absence of an energy barrier on the minimum energy path. When the collision energy increases, the ICSs decrease from a high value at low collision energy. The DCS results show that the angular distribution of the product molecules tends to the forward direction. Compared with the LiH 2 system, the NaH 2 system has a larger mass and the PES has a larger well at the H-NaH configuration, which leads to a higher ICS value in the H( 2 S) + NaH(X 1 Σ + ) → Na( 2 S) + H 2 (X 1 Σ g + ) reaction. Because the H( 2 S) + NaH(X 1 Σ + ) → Na( 2 S) + H 2 (X 1 Σ g + ) reaction releases more energy, the product molecules can be excited to a higher vibrational state.

  3. Effect of chloride substitution on the order–disorder transition in NaBH{sub 4} and Na{sup 11}BD{sub 4}

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, Jørn Eirik [Institute for Energy Technology, Physics Department, P.O. Box 40, NO-2027 Kjeller (Norway); Karen, Pavel [University of Oslo, Department of Chemistry, P.O. Box 1033 Blindern, NO-0315 Oslo (Norway); Sørby, Magnus H. [Institute for Energy Technology, Physics Department, P.O. Box 40, NO-2027 Kjeller (Norway); Hauback, Bjørn C., E-mail: bjorn.hauback@ife.no [Institute for Energy Technology, Physics Department, P.O. Box 40, NO-2027 Kjeller (Norway)

    2014-02-25

    Graphical abstract: Interactions that order the BD{sub 4}{sup -} tetrahedra below the order–disorder transition became increasingly frustrated by the solute in the Na({sup 11}BD{sub 4}){sub 1−x}Cl{sub x} solid solutions, and the order disappears at x = 0.158. Highlights: • The order–disorder transition temperature for Na(BH{sub 4}){sub 1−x}Cl{sub x} and Na({sup 11}BD{sub 4}){sub 1−x}Cl{sub x} is highly dependent on the Cl-content, x. • The transition is characterized by DSC for Na({sup 11}BD{sub 4}){sub 1−x}Cl{sub x} for x = 0, 0.10 and 0.15. • No transition is observed for x ⩾ 0.20 on cooling to 8 K. • The crystal structures are reported for Na{sup 11}BD{sub 4} at room temperature and 8 K and Na({sup 11}BD{sub 4}){sub 1−x}Cl{sub x} (x = 0.10, 0.15, 0.20 and 0.25) at 8 K from powder neutron diffraction. -- Abstract: Phase transition associated with anion disordering over two orientations in Na{sup 11}BD{sub 4} (NaBH{sub 4}) and its solid solutions with NaCl, Na({sup 11}BD{sub 4}){sub 1−x}Cl{sub x}, is investigated with powder diffraction (neutron and synchrotron radiation), differential scanning calorimetry and Raman spectroscopy. Upon heating, the transition temperature extrapolated to zero rate of heating is 192.2 K for Na{sup 11}BD{sub 4}, ΔS = 4.41 J/mol K, hysteresis 1.7 K and the volume increase 0.43%. Thermal parameters of the transition in Na({sup 11}BD{sub 4}){sub 1−x}Cl{sub x} follow a colligative-property model of an ideal solution, with x = 0.158(1) as the critical concentration at which the ordering interactions and the transition itself are eliminated. On approaching this limit, the tetragonal distortion of the ordered structure decreases somewhat towards the cubic average, and this is associated with a partial disorder of the tetrahedral anions seen by diffraction methods. In fact, a 3% disorder is already present in the pure solvent of the solid solution (Na{sup 11}BD{sub 4}) at 8 K.

  4. TweetNaCl : a crypto library in 100 tweets

    NARCIS (Netherlands)

    Bernstein, D.J.; van Gastel, B.; Janssen, W.; Lange, T.; Schwabe, P.; Smetsers, S.; Aranha, D.F.; Menezes, A.

    2015-01-01

    This paper introduces TweetNaCl, a compact reimplementation of the NaCl library, including all 25 of the NaCl functions used by applications. TweetNaCl is published on Twitter and fits into just 100 tweets; the tweets are available from anywhere, any time, in an unsuspicious way. Distribution via

  5. Na7 [Fe2S6 ] , Na2 [FeS2 ] and Na2 [FeSe2 ] : New 'reduced' sodium chalcogenido ferrates

    Science.gov (United States)

    Stüble, Pirmin; Peschke, Simon; Johrendt, Dirk; Röhr, Caroline

    2018-02-01

    Three new 'reduced' FeII containing sodium chalcogenido ferrates were obtained applying a reductive synthetic route. The mixed-valent sulfido ferrate Na7 [Fe2S6 ] , which forms bar-shaped crystals with metallic greenish luster, was synthesized in pure phase from natural pyrite and elemental sodium at a maximum temperature of 800 °C. Its centrosymmetric triclinic structure (SG P 1 bar , a = 764.15(2), b = 1153.70(2), c = 1272.58(3) pm, α = 62.3325 (7) , β = 72.8345 (8) , γ = 84.6394 (8) ° , Z = 3, R1 = 0.0185) exhibits two crystallographically different [Fe2S6 ] 7 - dimers of edge-sharing [FeS4 ] tetrahedra, with somewhat larger Fe-S distances than in the fully oxidized FeIII dimers of e.g. Na6 [Fe2III S6 ] . In contrast to the localized AFM ordered pure di-ferrates(III), the Curie-Weiss behavior of the magnetic susceptibility proves the rarely observed valence-delocalized S = 9/2 state of the mixed-valent FeIII /FeII dimer. The nearly spin-only value of the magnetic moment combined with the chemical bonding not generally differing from that in pure ferrates(II) and (III), provides a striking argument, that the reduction of the local Fe spin moments observed in all condensed sulfido ferrate moieties is connected with the AFM spin ordering. The two isotypic ferrates(II) Na2 [FeS2 ] and Na2 [FeSe2 ] with chain-like structural units (SG Ibam, a = 643.54(8)/ 660.81(1), b = 1140.2(2)/1190.30(2) c = 562.90(6)/585.59(1) pm, Z = 4, R1 = 0.0372/0.0466) crystallize in the K2 [ZnO2 ] -type structure. Although representing merely further members of the common series of chalcogenido metallates(II) Na2 [MIIQ2 ] , these two new phases, together with Na6 [FeS4 ] and Li2 [FeS2 ] , are the only examples of pure FeII alkali chalcogenido ferrates. The new compounds allow for a general comparison of di- and chain ferrates(II) and (III) and mixed-valent analogs concerning the electronic and magnetic properties (including Heisenberg super-exchange and double-exchange interactions

  6. ZAZNAVA IN VPLIV BARV NA PRIMERU TISKANIH OGLASOV

    OpenAIRE

    Spes, Katja

    2015-01-01

    V diplomski nalogi smo s pomočjo literature opisali simboliko osnovnih barv, vpliv, ki ga imajo na ljudi, ter njihov pomen v oglasnih sporočilih. Omejili smo se na tiskane oglase (plakate, časopise, revije, neposredno pošto in embalažo) in opisali njihove prednosti in slabosti. Z anketnim vprašalnikom smo ugotavljali, na katere barve smo najbolj pozorni in katerim lastnostim se posamezne barve bolj približajo. Osredotočili smo se na sedem barv

  7. Lipopolysaccharide hyperpolarizes guinea pig airway epithelium by increasing the activities of the epithelial Na(+) channel and the Na(+)-K(+) pump.

    Science.gov (United States)

    Dodrill, Michael W; Fedan, Jeffrey S

    2010-10-01

    Earlier, we found that systemic administration of lipopolysaccharide (LPS; 4 mg/kg) hyperpolarized the transepithelial potential difference (V(t)) of tracheal epithelium in the isolated, perfused trachea (IPT) of the guinea pig 18 h after injection. As well, LPS increased the hyperpolarization component of the response to basolateral methacholine, and potentiated the epithelium-derived relaxing factor-mediated relaxation responses to hyperosmolar solutions applied to the apical membrane. We hypothesized that LPS stimulates the transepithelial movement of Na(+) via the epithelial sodium channel (ENaC)/Na(+)-K(+) pump axis, leading to hyperpolarization of V(t). LPS increased the V(t)-depolarizing response to amiloride (10 μM), i.e., offset the effect of LPS, indicating that Na(+) transport activity was increased. The functional activity of ENaC was measured in the IPT after short-circuiting the Na(+)-K(+) pump with basolateral amphotericin B (7.5 μM). LPS had no effect on the hyperpolarization response to apical trypsin (100 U/ml) in the Ussing chamber, indicating that channel-activating proteases are not involved in the LPS-induced activation of ENaC. To assess Na(+)-K(+) pump activity in the IPT, ENaC was short-circuited with apical amphotericin B. The greater V(t) in the presence of amphotericin B in tracheas from LPS-treated animals compared with controls revealed that LPS increased Na(+)-K(+) pump activity. This finding was confirmed in the Ussing chamber by inhibiting the Na(+)-K(+) pump via extracellular K(+) removal, loading the epithelium with Na(+), and observing a greater hyperpolarization response to K(+) restoration. Together, the findings of this study reveal that LPS hyperpolarizes the airway epithelium by increasing the activities of ENaC and the Na(+)-K(+) pump.

  8. 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)

  9. Redetermination of Na(3)TaF(8).

    Science.gov (United States)

    Langer, Vratislav; Smrcok, Lubomír; Boca, Miroslav

    2010-09-01

    The crystal structure of trisodium octafluoridotantalate, Na(3)TaF(8), has been redetermined using diffractometer data collected at 153 K, resulting in more accurate bond distances and angles than obtained from a previous structure determination based on film data. The structure is built from layers running along [101], which are formed by distorted [TaF(8)] antiprisms and [NaF(6)] rectangular bipyramids sharing edges and corners. The individual layers are separated by eight-coordinated Na ions. Two atoms in the asymmetric unit are in special positions: the Ta atom is on a twofold axis in Wyckoff position 4e and one of the Na ions lies on an inversion centre in Wyckoff site 4d.

  10. ser precoce na intervenção

    OpenAIRE

    Bernardo, Ana Carolina Couto

    2013-01-01

    Dissertação apresentada à Universidade Fernando Pessoa como parte dos requisitos para obtenção do grau de Mestre em Ciências da Educação: Educação Especial, área de especialização em Domínio da Intervenção Precoce na Infância Este estudo centra-se na implementação de uma Escola de Mães, programa de educação parental realizado em seis sessões na freguesia de Calhetas, ilha de S. Miguel, e na avaliação comparativa, anterior e posterior ao programa, das três mães participantes no que...

  11. Na+/H+ exchange activity in the plasma membrane of Arabidopsis.

    Science.gov (United States)

    Qiu, Quan-Sheng; Barkla, Bronwyn J; Vera-Estrella, Rosario; Zhu, Jian-Kang; Schumaker, Karen S

    2003-06-01

    In plants, Na+/H+ exchangers in the plasma membrane are critical for growth in high levels of salt, removing toxic Na+ from the cytoplasm by transport out of the cell. The molecular identity of a plasma membrane Na+/H+ exchanger in Arabidopsis (SOS1) has recently been determined. In this study, immunological analysis provided evidence that SOS1 localizes to the plasma membrane of leaves and roots. To characterize the transport activity of this protein, purified plasma membrane vesicles were isolated from leaves of Arabidopsis. Na+/H+ exchange activity, monitored as the ability of Na to dissipate an established pH gradient, was absent in plants grown without salt. However, exchange activity was induced when plants were grown in 250 mm NaCl and increased with prolonged salt exposure up to 8 d. H+-coupled exchange was specific for Na, because chloride salts of other monovalent cations did not dissipate the pH gradient. Na+/H+ exchange activity was dependent on Na (substrate) concentration, and kinetic analysis indicated that the affinity (apparent Km) of the transporter for Na+ is 22.8 mm. Data from two experimental approaches supports electroneutral exchange (one Na+ exchanged for one proton): (a) no change in membrane potential was measured during the exchange reaction, and (b) Na+/H+ exchange was unaffected by the presence or absence of a membrane potential. Results from this research provide a framework for future studies into the regulation of the plant plasma membrane Na+/H+ exchanger and its relative contribution to the maintenance of cellular Na+ homeostasis during plant growth in salt.

  12. Thermophysical properties of Na2Th (MoO4)3 (s) and Na4Th (MoO4)4 (s)

    International Nuclear Information System (INIS)

    Dash, Smruti; Rakshit, S.K.; Singh, Ziley; Keskar, Meera; Dahale, N.D.

    2009-01-01

    The heat capacity of Na 2 Th (MoO 4 ) 3 (s) and Na 4 Th (MoO 4 ) 4 (s) have been measured by differential scanning calorimeter in the temperature range 318 to 845 K. The corresponding values are: C p,m (Na 2 Th (MoO 4 ) 3 ,s,T) (JK-1 mol-1) 368.710+ 1.0 10-1 (T/K) - 4950267 (K/T)2 (318 ≤ T (K) ≤ 845). C p,m (Na 4 Th (MoO 4 ) 4 ,s,T) (JK-1 mol-1) = 638.761+ 5.12 10-3 (T/K) - 12691691 (K/T)-2 (318 ≤ T (K) ≤ 845). Experimental heat capacity values for Na 2 Th (MoO 4 ) 3 (s) match reasonably well with that of additive oxide values. But C p,m (T) values of Na 4 Th (MoO 4 ) 4 (s) deviates substantially from the additive oxide values above 700 K. The uncertainty of the measurements reported in this study is calculated to be within 1 to 3 % . (author)

  13. Optimization and kinetics decomposition of monazite using NaOH

    International Nuclear Information System (INIS)

    MV Purwani; Suyanti; Deddy Husnurrofiq

    2015-01-01

    Decomposition of monazite with NaOH has been done. Decomposition performed at high temperature on furnace. The parameters studied were the comparison NaOH / monazite, temperature and time decomposition. From the research decomposition for 100 grams of monazite with NaOH, it can be concluded that the greater the ratio of NaOH / monazite, the greater the conversion. In the temperature influences decomposition 400 - 700°C, the greater the reaction rate constant with increasing temperature greater decomposition. Comparison NaOH / monazite optimum was 1.5 and the optimum time of 3 hours. Relations ratio NaOH / monazite with conversion (x) following the polynomial equation y = 0.1579x 2 – 0.2855x + 0.8301 (y = conversion and x = ratio of NaOH/monazite). Decomposition reaction of monazite with NaOH was second orde reaction, the relationship between temperature (T) with a reaction rate constant (k), k = 6.106.e - 1006.8 /T or ln k = - 1006.8/T + 6.106, frequency factor A = 448.541, activation energy E = 8.371 kJ/mol. (author)

  14. The loss of Na and Cl during the pyrolysis of a NaCl-loaded brown coal sample

    Energy Technology Data Exchange (ETDEWEB)

    Mody, D.; Li, C.Z.

    1999-07-01

    A Victorian brown coal was physically loaded with NaCl and pyrolyzed in a quartz fluidized-bed reactor. The fluidized-bed reactor was equipped with a quartz frit in the freeboard zone to enable the total devolatilization of the coal particles. The introduction of NaCl into the coal has caused only minor reductions in the weight loss. A significant amount of chlorine was volatilized during pyrolysis at temperatures as low as 200 C. At temperatures around 400--500 C where the loss of sodium was not very significant, about 70% of chlorine was volatilized from the coal particles. With the volatilization of chlorine at this temperature level, sodium must have been bonded to the char matrix. With increasing temperature, the volatilization of chlorine decreased and then increased again, whereas the volatilization of sodium increased monotonically with increasing temperature. Almost all the Na in coal could be volatilized at temperatures higher than about 800 C. These experimental results clearly indicate that chlorine and Na interacted strongly with coal/char at high temperatures. Na and Cl in the coal did not volatilize as NaCl molecules. Significant amounts of species containing a COO-group such as acetate, formate and oxalate were observed in the pyrolysis products although the exact forms of these species (i.e., as acids, salts or esters) in the pyrolysis product remain unknown. The yields of the species containing a COO-group decreased with increasing temperature, possibly due to the intensified thermal cracking reactions at high temperatures.

  15. Avaliação do tratamento térmico na composição química e na qualidade da cajuína Evaluation of the thermal treatment on the chemical composition and quality of "cajuína" beverage

    Directory of Open Access Journals (Sweden)

    Ronaldo Ferreira do Nascimento

    2003-08-01

    Full Text Available Neste trabalho foi estudado o efeito do processo de tratamento térmico na qualidade e composição química da bebida cajuína quando submetida ao cozimento sob temperatura constante de 100ºC durante 1:00, 1:30, 2:00, 2:30, 3:00 e 4:00 horas. Alíquotas foram coletadas em cada tempo de aquecimento e analisadas por cromatografia líquida de alta eficiência (CLAE em relação aos ácidos (cítrico e ascórbico, aldeídos furânicos (5-hidroximetilfurfural e furfural e açúcares (frutose, glicose e frutose. Os resultados foram reprodutíveis e indicaram que as cajuínas comerciais do estado do Ceará apresentam uma grande diversidade quanto ao processo de cozimento e ao teor de vitamina C, causados principalmente por processos térmicos inadequados. O tempo mais adequado sugerido para o "cozimento" da cajuína está em torno de 2:00h. O trabalho também aponta a combinação das análises de 5-HMF, furfural, ácido ascórbico e teor de ácido ascórbico/ácido cítrico como uma metodologia alternativa para a avaliação da qualidade da cajuína.In this work the effect of the thermal process on the quality and chemical composition of the beverage cajuína was studied. Cajuína is basically clarified cashew juice. Samples of cajuína were submitted to thermal processes, of constant heating (100ºC for 1:00, 1:30, 2:00, 2:30, 3:00 and 4:00 hours. The samples were subsequently analyzed by HPLC for glucose, fructose, citric acid, ascorbic acid, hydroxymethylfurfural (5-HMF and furfural. The results showed that the commercial cajuína beverage of Ceará State presented a great diversity in process standardization and vitamin C content, caused by inadequate thermal processing. The process is more efficient with a time period of 2:00hs. The work also indicates a combination of the analyses of 5-HMF, furfural and ascorbic acid and the ratio ascorbic acid/citric acid, as an alternative methodology for the evaluation of cajuína quality.

  16. Measurement and modeling of CO2 solubility in NaCl brine and CO2–saturated NaCl brine density

    DEFF Research Database (Denmark)

    Yan, Wei; Huang, Shengli; Stenby, Erling Halfdan

    2011-01-01

    over climate change and energy security. This work is an experimental and modeling study of two fundamental properties in high pressure CO2–NaCl brine equilibrium, i.e., CO2 solubility in NaCl brine and CO2–saturated NaCl brine density. A literature review of the available data was presented first...

  17. Five ab initio potential energy and dipole moment surfaces for hydrated NaCl and NaF. I. Two-body interactions

    International Nuclear Information System (INIS)

    Wang, Yimin; Bowman, Joel M.; Kamarchik, Eugene

    2016-01-01

    We report full-dimensional, ab initio-based potentials and dipole moment surfaces for NaCl, NaF, Na + H 2 O, F − H 2 O, and Cl − H 2 O. The NaCl and NaF potentials are diabatic ones that dissociate to ions. These are obtained using spline fits to CCSD(T)/aug-cc-pV5Z energies. In addition, non-linear least square fits using the Born-Mayer-Huggins potential are presented, providing accurate parameters based strictly on the current ab initio energies. The long-range behavior of the NaCl and NaF potentials is shown to go, as expected, accurately to the point-charge Coulomb interaction. The three ion-H 2 O potentials are permutationally invariant fits to roughly 20 000 coupled cluster CCSD(T) energies (awCVTZ basis for Na + and aVTZ basis for Cl − and F − ), over a large range of distances and H 2 O intramolecular configurations. These potentials are switched accurately in the long range to the analytical ion-dipole interactions, to improve computational efficiency. Dipole moment surfaces are fits to MP2 data; for the ion-ion cases, these are well described in the intermediate- and long-range by the simple point-charge expression. The performance of these new fits is examined by direct comparison to additional ab initio energies and dipole moments along various cuts. Equilibrium structures, harmonic frequencies, and electronic dissociation energies are also reported and compared to direct ab initio results. These indicate the high fidelity of the new PESs.

  18. Threshold oxygen levels in Na(I) for the formation of NaCrO 2(s) on 18-8 stainless steels from accurate thermodynamic measurements

    Science.gov (United States)

    Sreedharan, O. M.; Madan, B. S.; Gnanamoorthy, J. B.

    1983-12-01

    The compound NaCrO 2(s) is an important corrosion product in sodium-cooled LMFBRs. The standard Gibbs energy of formation of NaCrO 2(s) is required for the computation of threshold oxygen levels in Na(1) for the formation of NaCrO 2(s) on 18-8 stainless steels. For this purpose the emf of the galvanic cell: Pt, NaCrO 2, Cr 2O 3, Na 2CrO 4/15 YSZ/O 2 ( P O 2 = 0.21 atm, air), Pt was measured over 784-1012 K to be: (E±4.4)(mV) = 483.67-0.34155 T(K). From this, the standard Gibbs energy of formation of NaCrO 2(s) from the elements ( ΔG f,T0) and from the oxides ( ΔG f,OX,T0) was calculated to be: [ΔG f,T0(NaCrO 2, s)±1.86] (kJ/mol) =-869.98 + 0.18575 T(K) , [ΔG f,OX,T0(NaCr0 2, s)±4.8] (kJ/mol) = -104.25-0.00856 T(K) . The molar heat capacity, C P0, of NaCrO 2(s) was measured by DSC to be (350-600 K): C P0(NaCrO 2, s) (J/K mol) = 27.15 + 0.1247 T (K) , From these data, values of -99.3 kJ/mol and 91.6 J/K mol were computed for ΔH f,2980 and S 2980 of NaCrO 2(s). The internal consistency was checked with the use of enthalpy data on Na 2CrO 4(s). From the standard Gibbs energy of formation of NaCrO 2(s) the equation logC 0(wppm) = 3.9905-3147.6 T(K) was derived, where C 0 is the threshold oxygen level for the formation of NaCrO 2(s) on 18-8 stainless steels.

  19. PRIMERJAVA GEODETSKIH METOD NA ZAHTEVNEM GRADBENEM OBJEKTU

    OpenAIRE

    Reberčnik, Matic

    2017-01-01

    V projektni nalogi smo v uvodnih poglavjih predstavili različne načine izvajanja geodetskih meritev, ki jih v gradbeništvu uporabljamo pri analizi pomikov in deformacij gradbenih konstrukcij ter terena, na katerem so le-te postavljene. V nadaljevanju opisujemo terestične in GNSS (globalni navigacijski satelitski sistem) metode, ki smo jih uporabljali pri izvajanju meritev na izbranem premostitvenem objektu avtocestnega odseka v Sloveniji (zaradi varovanja podatkov ga imenujemo Objekt 1). Pod...

  20. Synthesis of Li(x)Na(2-x)Mn2S3 and LiNaMnS2 through redox-induced ion exchange reactions

    International Nuclear Information System (INIS)

    Luthy, Joshua A.; Goodman, Phillip L.; Martin, Benjamin R.

    2009-01-01

    Na 2 Mn 2 S 3 was oxidatively deintercalated using iodine in acetonitrile to yield Na 1.3 Mn 2 S 3 , with lattice constants nearly identical to that of the reactant. Lithium was then reductively intercalated into the oxidized product to yield Li 0.7 Na 1.3 Mn 2 S 3 . When heated, this metastable compound decomposed to form a new crystalline compound, LiNaMnS 2 , along with MnS and residual Na 2 Mn 2 S 3 . Single crystal X-ray diffraction structural analysis of LiNaMnS 2 revealed that this compound crystallizes in P-3m1 with cell parameters a=4.0479(6) A, c=6.7759(14) A, V=96.15(3) A 3 (Z=1, wR2=0.0367) in the NaLiCdS 2 structure-type. - Graphical abstract: Structure of LiNaMnS 2 . Li and Mn are statistically distributed in edge-shared tetrahedral environments linked into infinite planes. Sodium ions occupy interlayer sites

  1. Número de amostras na análise geoestatística e na krigagem de mapas de atributos do solo

    Directory of Open Access Journals (Sweden)

    Zigomar Menezes de Souza

    2014-02-01

    Full Text Available O objetivo deste trabalho foi analisar diferentes intensidades de amostragem do solo com relação à precisão na análise geoestatística e interpolação de mapas, para fins de agricultura de precisão em área de cana-de-açúcar. O solo foi coletado em duas grades regulares na profundidade de 0,00-0,20m para análise granulométrica (área 1 e da fertilidade do solo (área 2. Foram comparadas intensidades de amostragem do solo: 208, 105, 58 e 24 pontos na área 1 e 206, 102 e 53 pontos na área 2. Os dados foram submetidos à análise descritiva e geoestatística. Os variogramas construídos com 105 pontos não diferem dos variogramas com 208 pontos, fato que não ocorre para 58 e 24 pontos. O aumento do intervalo de amostragem e a redução do número de pontos promovem o maior erro na estimativa por krigagem. As amostragens com mais de 100 pontos por área não resultaram em melhorias significativas no erro da estimativa por krigagem, nem diferiram na quantidade de insumos aplicados em campo.

  2. Corpo-escrita na esquizofrenia

    OpenAIRE

    Bialer, Marina

    2014-01-01

    Este artigo aborda a importância do trabalho de escrita na esquizofrenia. Toma-se como ponto de partida a formulação lacaniana sobre o esquizofrênico como aquele que não tem as funções dos órgãos do seu corpo dadas pelos discursos estabelecidos. A hipótese de que o trabalho sobre a letra pode permitir o tratamento do gozo debordante na esquizofrenia é analisada pelo estudo da obra do escritor esquizofrênico Robert Walser, a qual evidencia a viabilidade da construção de um corpo pela escrita n...

  3. Chemisorption of Na on the Ti Nanoparticle surface and its effects on the Na-H{sub 2}O reaction reactivity

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Soo Jae; Park, Gunyeop; Baek, Jehyun; Park, Hyun Sun [POSTECH, Pohang (Korea, Republic of); Kim, Moo Hwan [Korea institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    This accident showed that elimination of SWR risk should be one of the most significant design criteria for the development of safe SFRs. Design solutions to ensure isolation of the Na from the water have been proposed; these include double-walled structures in the steam generator and at coolant boundaries and guard vessels or guard piping lines filled with inert gas. However, those methods cannot be ultimate solutions because the system still has a possibility of failure. An alternative approach to reduce the severity of the SWR is to reduce the reactivity of Na. Recently, this goal has been achieved by suspending a small amount of Ti nanoparticles (NPs) in liquid Na. Adding 2 at% of 10-nm Ti NPs in liquid Na reduced the heat of the reaction up to 80% and H{sub 2} production rate by 10%. The number of adsorbed Na atoms onto Ti NPs with respect to the various temperature and pressure was calculated by using ab-initio and thermodynamics. Furthermore, the model which relates the Na chemisorption and SWR reactivity was proposed. The repression of SWR by Ti NPs was expected to be caused by strong chemical interaction between Ti NP surface and Na atoms; ab initio calculation using density functional theory and atomistic thermodynamic approach were conducted to test this hypothesis. Adsorption of 0.25ML Na at hcp hollow sites was the most favorable adsorption surface state and strong chemical adsorption was confirmed by the adsorption energy of -1.65 eV. A covalent-like metallic bond was confirmed between adsorbed Na and Ti atoms on the Ti(0001) surface; this bond affects the hydration energy of Na atoms and the activation barrier of the SWR. Using adsorption energy from the ab-initio calculation and atomistic thermodynamics, the thermodynamically most stable adsorption state at (T,P) was determined Na chemisorption effect on the SWR reactivity regression rate is modeled. The model predict χ variation with respect to time well especially dramatic reduction of χ; the

  4. O apelo ecológico na propaganda como fator de influência na atitude de compra do consumidor: um estudo experimental

    OpenAIRE

    Santos, João Maurício

    2010-01-01

    Este estudo examinou o apelo ecológico utilizado na propaganda como influenciador na atitude de compra do consumidor, tendo em vista que nas duas últimas décadas houve um crescimento nos anúncios que utilizam este tipo de apelo, demonstrando que, pelo surgimento de um novo nicho de mercado, empresas têm se valido do marketing verde e da influência normativa na sua estratégia de marketing. Buscou-se investigar se efetivamente o uso do apelo ecológico na propaganda influencia pos...

  5. Dejavniki psihološkega nasilja na delovnem mestu

    OpenAIRE

    Ilc, Teja

    2011-01-01

    Raziskave na področju delovnih razmer kažejo, da je danes pereč problem ravno psihološko nasilje na delovnem mestu. Posebna oblika psihološkega nasilja na delovnem mestu je mobing, s katerim se v praksi srečujemo vsak dan, vendar se ga pogosto ne zavedamo. Namen magistrske naloge je pojasniti pojem in pomen mobinga v delovnih organizacijah, poiskati možne vzroke in posledice, ki vplivajo na ta pojav, ter predlagati rešitve. Poznavanje mehanizmov, ki povzročajo mobing, njegovih vzrokov in...

  6. Anisotropy and polarization in charge changing collisions of C4+ with Na(3s) and laser aligned Na(3p)

    NARCIS (Netherlands)

    Hoekstra, R; Morgenstern, R; Olson, RE

    1996-01-01

    Absolute cross sections for C3+(6-->5) emission at 465.7 nm after collisions of C4+ ions with ground state Na(3s) and laser excited aligned Na(Sp) atoms are measured over the collision energy range of 3-7 keV amu(-1). For Na(3s) polarizations are observed by measuring the linear polarization of the

  7. Efeito da dexametasona e do cetoprofeno na osteogênese e na resistência óssea em ratos

    Directory of Open Access Journals (Sweden)

    Patrícia Costa dos Santos da Silva

    2012-04-01

    Full Text Available O presente estudo teve como objetivo avaliar o efeito do cetoprofeno e da dexametasona na osteogênese ao redor de implante de hidroxiapatita densa (HAD na tíbia, no osso parietal, e na resistência óssea. Utilizaram-se 15 ratos Wistar, pesando 250±30 g, com 50 dias de idade. Após a anestesia com quetamina/xilazina IM, produziuse no osso parietal e na epífise proximal da tíbia uma cavidade de 3 mm, sendo implantada a HAD. Após a cirurgia os animais foram divididos em três grupos (n=5: controle (CT, anti-inflamatório não esteroidal (AINES e anti-inflamatório esteroidal (AIES. O grupo AINES foi submetido ao tratamento com cetoprofeno na dose de 12 mg/Kg/dia, o AIES recebeu doses de 0,10 mg/kg/dia de dexametasona o grupo CT recebeu solução fisiológica 0,9% (SF por via subcutânea durante 30 dias. Todos os grupos receberam a mesma dieta sólida e água ad libitum. Após 30 dias de experimento os animais sofreram eutanásia, os fêmures coletados, para teste mecânico, e os locais do implante das tíbias e o osso parietal, para análise histomorfométrica. Os grupos AINES e AIES apresentaram menor volume de osso neoformado na falha óssea e ao redor do implante de HAD , como também, menor força máxima para a ruptura completa dos fêmures, quando comparados com o grupo CT. O uso do cetoprofeno e a dexametasona interferiram na osteogênese ao redor do implante de HAD e no osso parietal, diminuindo a resistência óssea principalmente pela inibição da COX2 e diminuição das prostaglandinas, comprometendo a estabilidade e manutenção do implante.

  8. Nalaz tombusvirusa na vrsti Erigeron canadensis L.

    OpenAIRE

    Jeknić, Zoran; Erić, Živojin; Grbelja, Julijana

    1988-01-01

    Iz listova zaraženih primjeraka korovne biljke Erigeron canadensis L. koji su rasli na nekoliko lokaliteta u Sarajevu izoliran je virus iz skupine tombusvirusi. Identifikacija virusa izvršena je na osnovi reakcije pokusnih biljaka, analize ultratankih presjeka kroz zaraženo tkivo, morfologije i veličine virusnih čestica, te na osnovi seroloških reakcija metodom dvostruke imunodifuzije u agarskom gelu i čvrsto fazne imunoelektronske mikroskopije (SPIEM). U serološkim pokusima upotrijebljen je ...

  9. Transcriptional regulators of Na, K-ATPase subunits

    OpenAIRE

    Zhiqin eLi; Sigrid A Langhans

    2015-01-01

    The Na,K-ATPase classically serves as an ion pump creating an electrochemical gradient across the plasma membrane that is essential for transepithelial transport, nutrient uptake and membrane potential. In addition, Na,K-ATPase also functions as a receptor, a signal transducer and a cell adhesion molecule. With such diverse roles, it is understandable that the Na,K-ATPase subunits, the catalytic alpha-subunit, the beta-subunit and the FXYD proteins, are controlled extensively during developme...

  10. NaIrO3-A pentavalent post-perovskite

    International Nuclear Information System (INIS)

    Bremholm, M.; Dutton, S.E.; Stephens, P.W.; Cava, R.J.

    2011-01-01

    Sodium iridium (V) oxide, NaIrO 3, was synthesized by a high pressure solid state method and recovered to ambient conditions. It is found to be isostructural with CaIrO 3 , the much-studied structural analog of the high-pressure post-perovskite phase of MgSiO 3 . Among the oxide post-perovskites, NaIrO 3 is the first example with a pentavalent cation. The structure consists of layers of corner- and edge-sharing IrO 6 octahedra separated by layers of NaO 8 bicapped trigonal prisms. NaIrO 3 shows no magnetic ordering and resistivity measurements show non-metallic behavior. The crystal structure, electrical and magnetic properties are discussed and compared to known post-perovskites and pentavalent perovskite metal oxides. -- Graphical abstract: Sodium iridium(V) oxide, NaIrO 3 , synthesized by a high pressure solid state method and recovered to ambient conditions is found to crystallize as the post-perovskite structure and is the first example of a pentavalent ABO 3 post-perovskite. Research highlights: → NaIrO 3 post-perovskite stabilized by pressure. → First example of a pentavalent oxide post-perovskite. → Non-metallic and non-magnetic behavior of NaIrO 3 .

  11. LiVO/sub 3/-Li/sub 2/Mo(W)O/sub 4/ and NaVO/sub 3/-Na/sub 2/Cr(Mo)O/sub 4/ systems

    Energy Technology Data Exchange (ETDEWEB)

    Belyaev, I N; Lupeiko, T G; Vyalikova, V I [Rostovskij-na-Donu Gosudarstvennyj Univ. (USSR)

    1975-09-01

    The systems LiVO/sub 3/-Li/sub 2/MoO/sub 4/, LiVO/sub 3/-Li/sub 2/WO/sub 4/, NaNO/sub 3/-Na/sub 2/CrO/sub 4/, NaNO/sub 3/-Na/sub 2/MoO/sub 4/ were studied with thermographic and partially visual polythermal methods of physical and chemical analyses. Except NaVO/sub 3/-Na/sub 2/MoO/sub 4/ all investigated systems are eutectic ones with limited solid solutions on the basis of some component; the eutectics melt at 542, 544, 550/sup 0/C and contain 25, 20 and 26% of Li/sub 2/MoO/sub 4/, Li/sub 2/WO/sub 4/ and Na/sub 2/CrO/sub 4/ respectively. The system NaNO/sub 3/-Na/sub 2/MoO/sub 4/ contains compound 18 NaVO/sub 3/.11Na/sub 2/MoO/sub 4/ congruently melting at 570/sup 0/C. Two eutectics of the system have melting points at 542 and 548/sup 0/C and contain 47 and 67% of Na/sub 2/MoO/sub 4/.

  12. DRUŽBENA OMREŽJA NA INTERNETU

    OpenAIRE

    Ploj, Alen

    2013-01-01

    Družbena omrežja na spletu so zadnje čase zelo popularen način posredne komunikacije in predstavljajo naš vsakdan. Uporaba je enostavna in hitra, učinkovitost pa neverjetna. Zaradi priljubljenosti družbenih omrežij se njihove uporabe poslužujejo tudi različne organizacije, ki z njihovo pomočjo širijo obseg svojega delovanja ter obveščanja uporabnikov o svojih izdelkih/storitvah (marketing). Kot vsako donosno tržišče je tudi internetno tržišče nasičeno z družbenimi omrežji, ki ponujajo najr...

  13. O Platonismo de Russell na metafísica e na matemática

    Directory of Open Access Journals (Sweden)

    Guido Imaguire

    2005-06-01

    Full Text Available Neste artigo, analiso o surgimento e a superação do Platonismo em B. Russell, tanto na sua filosofia da matemática como na sua metafísica. Começo por explicitar os argumentos que levaram Russell a aderir ao chamado "Platonismo Proposicional" - posição que será tecnicamente relevante na definição de números. Na seção seguinte, discutirei até que ponto a teoria das descrições definidas determina, necessariamente, uma adesão ao nominalismo, e as dificuldades que surgem para o logicismo conseqüentes do abandono do platonismo. Finalmente, mostrarei como a posição madura de Russell caracteriza-se mais como um reducionismo do que propriamente como um nominalismo, e como este é fundado no princípio do mínimo vocabulário.In this paper, I analyze the emergence and the overcoming of Platonism both in Russell's philosophy of mathematics and his metaphysics. I begin by examining the arguments which led Russell to endorse a position that I term "Propositional Platonism" - this position proves to be relevant for Russell's definition of numbers. In the following section, I address the question of the extent to which Russell's theory of descriptions implies the acceptance of nominalism. Moreover, I examine the difficulties which arise for logicism, if it no longer goes hand in hand with platonism. Finally, I argue argue that Russell's mature position is to be characterized as a form of reductionism rather than as a variant of nominalism

  14. Five ab initio potential energy and dipole moment surfaces for hydrated NaCl and NaF. I. Two-body interactions

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Yimin, E-mail: yimin.wang@emory.edu; Bowman, Joel M., E-mail: jmbowma@emory.edu [Department of Chemistry, Cherry L. Emerson Center for Scientific Computation, Emory University, Atlanta, Georgia 30322 (United States); Kamarchik, Eugene, E-mail: eugene.kamarchik@gmail.com [Quantum Pomegranate, LLC, 2604 Kings Lake Court NE, Atlanta, Georgia 30345 (United States)

    2016-03-21

    We report full-dimensional, ab initio-based potentials and dipole moment surfaces for NaCl, NaF, Na{sup +}H{sub 2}O, F{sup −}H{sub 2}O, and Cl{sup −}H{sub 2}O. The NaCl and NaF potentials are diabatic ones that dissociate to ions. These are obtained using spline fits to CCSD(T)/aug-cc-pV5Z energies. In addition, non-linear least square fits using the Born-Mayer-Huggins potential are presented, providing accurate parameters based strictly on the current ab initio energies. The long-range behavior of the NaCl and NaF potentials is shown to go, as expected, accurately to the point-charge Coulomb interaction. The three ion-H{sub 2}O potentials are permutationally invariant fits to roughly 20 000 coupled cluster CCSD(T) energies (awCVTZ basis for Na{sup +} and aVTZ basis for Cl{sup −} and F{sup −}), over a large range of distances and H{sub 2}O intramolecular configurations. These potentials are switched accurately in the long range to the analytical ion-dipole interactions, to improve computational efficiency. Dipole moment surfaces are fits to MP2 data; for the ion-ion cases, these are well described in the intermediate- and long-range by the simple point-charge expression. The performance of these new fits is examined by direct comparison to additional ab initio energies and dipole moments along various cuts. Equilibrium structures, harmonic frequencies, and electronic dissociation energies are also reported and compared to direct ab initio results. These indicate the high fidelity of the new PESs.

  15. Recovery of the heavy elements by NaY AND NaZSM-5 sorbant materials

    International Nuclear Information System (INIS)

    Nibou, D.; Lebail, S.

    1997-04-01

    Porous sorbants as zeolites have a several applications in differents fiels: industrial gas purification, catalysis, transformation hydrocarbures prosesses and exchange ions. The hiogh capacity to exchange their cations with those of aqueous solutions was known (1). Since the accession of synthetic zeolites, these silicates have invaded the market and the firstindustrial applications were in exchange field. Studies at Battelle Northwest in Rchland, Washington have shown that zeolites may be used in treatment of radioactive wastes (2). The used method for storing the isotopes is based on selective removal by ion exchange. Clinoptilolite, zeolite (modernite), NaA, and AW-500 have been used. In this context, the present work deals with the recovery of heavy metals like lead and uranium using some microporous materials. The obtained results show that NaY faujasite and NaZSM-5 of the FAU- and MFI-type structure respectively are very effective in removing these elements from waste water

  16. Hali ya taaluma ya ukalimani Tanzania: jana, leo na kesho ...

    African Journals Online (AJOL)

    Umuhimu wa ukalimani katika mawasiliano umeongezeka kutokana na utandawazi. Utandawazi umerahisisha kukutanika na kuwasiliana kwa watu wazungumzao lugha tofauti kupitia wakalimani. Kutokana na ongezeko hilo la umuhimu wa ukalimani, kumekuwa na jitihada mbalimbali katika nchi mbalimbali kuhakikisha ...

  17. Minimizing Load Effects on NA4 Gear Vibration Diagnostic Parameter

    Science.gov (United States)

    Dempsey, Paula J.; Zakrajsek, James J.

    2001-01-01

    NA4 is a vibration diagnostic parameter, developed by researchers at NASA Glenn Research Center, for health monitoring of gears in helicopter transmissions. The NA4 reacts to the onset of gear pitting damage and continues to react to the damage as it spreads. This research also indicates NA4 reacts similarly to load variations. The sensitivity of NA4 to load changes will substantially affect its performance on a helicopter gearbox that experiences continuously changing load throughout its flight regimes. The parameter NA4 has been used to monitor gear fatigue tests at constant load. At constant load, NA4 effectively detects the onset of pitting damage and tracks damage severity. Previous research also shows that NA4 reacts to changes in load applied to the gears in the same way it reacts to the onset of pitting damage. The method used to calculate NA4 was modified to minimize these load effects. The modified NA4 parameter was applied to four sets of experimental data. Results indicate the modified NA4 is no longer sensitive to load changes, but remains sensitive to pitting damage.

  18. Secretory NaCl and volume flow in renal tubules.

    Science.gov (United States)

    Beyenbach, K W

    1986-05-01

    This review attempts to give a retrospective survey of the available evidence concerning the secretion of NaCl and fluid in renal tubules of the vertebrate kidney. In the absence of glomerular filtration, epithelial secretory mechanisms, which to this date have not been elucidated, are responsible for the renal excretion of NaCl and water in aglomerular fish. However, proximal tubules isolated from glomerular fish kidneys of the flounder, killifish, and the shark also have the capacity to secrete NaCl and fluid. In shark proximal tubules, fluid secretion appears to be driven via secondary active transport of Cl. In another marine vertebrate, the sea snake, secretion of Na (presumably NaCl) and fluid is observed in freshwater-adapted and water-loaded animals. Proximal tubules of mammals can be made to secrete NaCl in vitro together with secretion of aryl acids. An epithelial cell line derived from dog kidney exhibits secondary active secretion of Cl when stimulated with catecholamines. Tubular secretion of NaCl and fluid may serve a variety of renal functions, all of which are considered here. The occurrence of NaCl and fluid secretion in glomerular proximal tubules of teleosts, elasmobranchs, and reptiles and in mammalian renal tissue cultures suggests that the genetic potential for NaCl secretion is present in every vertebrate kidney.

  19. Mechanochemical transformations in Li(Na)AlH{sub 4}-Li(Na)NH{sub 2} systems

    Energy Technology Data Exchange (ETDEWEB)

    Dolotko, Oleksandr [Ames Laboratory of the U.S. DOE, Iowa State University, Ames, IA 50011-3020 (United States); Zhang Haiqiao [Ames Laboratory of the U.S. DOE, Iowa State University, Ames, IA 50011-3020 (United States); Department of Materials Science and Engineering, Iowa State University, Ames, IA 50011-2300 (United States); Ugurlu, Ozan [Ames Laboratory of the U.S. DOE, Iowa State University, Ames, IA 50011-3020 (United States); Department of Materials Science and Engineering, Iowa State University, Ames, IA 50011-2300 (United States); Wiench, Jerzy W. [Ames Laboratory of the U.S. DOE, Iowa State University, Ames, IA 50011-3020 (United States); Pruski, Marek [Ames Laboratory of the U.S. DOE, Iowa State University, Ames, IA 50011-3020 (United States); Scott Chumbley, L. [Ames Laboratory of the U.S. DOE, Iowa State University, Ames, IA 50011-3020 (United States); Department of Materials Science and Engineering, Iowa State University, Ames, IA 50011-2300 (United States); Pecharsky, Vitalij [Ames Laboratory of the U.S. DOE, Iowa State University, Ames, IA 50011-3020 (United States) and Department of Materials Science and Engineering, Iowa State University, Ames, IA 50011-2300 (United States)]. E-mail: vitkp@ameslab.gov

    2007-05-15

    Mechanochemical transformations of tetrahydroaluminates and amides of lithium and sodium have been investigated using gas volumetric analysis, X-ray powder diffraction, solid-state nuclear magnetic resonance (NMR) and transmission electron microscopy. In a transformation of LiAlH{sub 4} and LiNH{sub 2} taken in an 1:1 molar ratio, the amount of released hydrogen (6.6 wt.% after 30 min ball milling) was higher than in any known one pot mechanochemical process involving a hydrogen-containing solid. A total of 4.3 wt.% of hydrogen is released by the NaAlH{sub 4}-NaNH{sub 2} system after 60 min ball milling; and 5.2 wt.% H{sub 2} is released when LiAlH{sub 4} and NaNH{sub 2} or NaAlH{sub 4} and LiNH{sub 2} are ball milled for 90 min and 120 min, respectively. All transformations proceed at room temperature. The mechanism of the overall transformation MAlH{sub 4}(s) + MNH{sub 2}(s) {sup {yields}} 2MH(s) + AlN(s) + 2H{sub 2}(g) was identified based on detailed spectroscopic analysis of the intermediate (M{sub 3}AlH{sub 6}) and final products of the ball milling process.

  20. Ética na pesquisa em Administração

    OpenAIRE

    Leite, Ana Patrícia Rodrigues

    2012-01-01

    A ética na pesquisa científica é um tema abordado e muito discutido em diversas áreas do conhecimento ligadas à saúde. Na área da Administração, são raros os estudos que abordam o tema da ética na pesquisa. O presente estudo buscou preencher esta lacuna na produção do conhecimento sobre o tema, investigando como os princípios éticos encontrados na literatura e nos códigos de conduta são percebidos e considerados nas atividades de pesquisa em Administração, desenvolvidas por pes...

  1. NA48 experiment : view along the NA48 beamline with the detector in the distance.

    CERN Multimedia

    Hans Taureg

    1996-01-01

    Photo 02: Side view of the NA48 experiment showing the LKR calorimeter cryostat No one is sure why the Universe wound up the way it has: all matter and no antimatter. According to prevailing theories, the early universe had equal amounts of matter and antimatter. To see what might be missing from the theories, physicists search for the rare cases in which matter and antimatter behave differently. One such imbalance, called direct CP violation, showed up in the NA 31 experiment at CERN. The results from this experiment, first presented in 1993, showed that when K mesons and their antimatter cousins decay, they show a slight preference for matter over antimatter. Later experiments with neutral K mesons, including NA48 at CERN and KTeV at Fermilab in the United States, showed direct CP violation is real.

  2. Microhardness studies on as-grown faces of NaClO3 and NaBrO3 ...

    Indian Academy of Sciences (India)

    Unknown

    studies are made on as-grown faces of these crystals at various loads. Typical cracks are ... crystals is around 1⋅6 suggesting that these are moderately harder samples. ... the values of elastic constants (C44) and are found to be close to the experimental results. ..... the structure of NaClO3 and NaBrO3 is not as simple as.

  3. Thermodiffusive behaviour of NaCl and KCl aqueous solutions a model for the Na-K pump

    International Nuclear Information System (INIS)

    Gaeta, F.S.; Mita, D.G.; Perna, G.; Scala, G.

    1975-01-01

    In NaCl and KCl aqueous nonisothermal solutions K + inverts its sense of migration within the physiological concentration range; Na + behaves similarly at much lower concentrations. These findings are discussed in relation to solute induced modifications of water structure and of their influence on thermal diffusion. A possible evolutionary model of a thermodiffusive mechanism for the sodium potassium pump is also suggested

  4. ANALIZA UPORABNIŠKIH VMESNIKOV NA MOBILNIH NAPRAVAH

    OpenAIRE

    Bohak, Gregor

    2012-01-01

    V diplomskem delu smo predstavili pravila in smernice oblikovanja uporabniških vmesnikov na mobilnih napravah. Omejili smo se na platforme Google Android, Nokia Symbian, Nokia MeeGo, Apple iOS ter Microsoft Windows Phone 7. Za vsako izmed platform smo predstavili splošen model uporabniškega vmesnika, splošen model uporabniškega vmesnika aplikacije, navigacijske vzorce ter gradnike. Vse skupaj tudi smo obogatili z veliko grafičnega materiala. V drugem delu smo na podlagi pridobljenega znanja p...

  5. Role of alkali carbonate and salt in topochemical synthesis of K1/2Na1/2NbO3 and NaNbO3 templates

    Science.gov (United States)

    Lee, Jae-Seok; Jeon, Jae-Ho; Choi, Si-Young

    2013-11-01

    Since the properties of lead-free piezoelectric materials have thus far failed to meet those of lead-based materials, either chemical doping or morphological texturing should be employed to improve the piezoelectric properties of lead-free piezoelectric ceramics. The goal of this study was to synthesize plate-like K1/2Na1/2NbO3 and NaNbO3 particles, which are the most favorable templates for morphological texturing of K1/2Na1/2NbO3 ceramics. To achieve this goal, Bi2.5Na3.5Nb5O18 precursors in a plate-like shape were first synthesized and subsequently converted into K1/2Na1/2NbO3 or NaNbO3 particles that retain the morphology of Bi2.5Na3.5Nb5O18. In this study, we found that sodium or potassium carbonate does not play a major role in converting the Bi2.5Na3.5Nb5O18 precursor to K1/2Na1/2NbO3 or NaNbO3, on the contrary to previous reports; however, the salt contributes to the conversion reaction. All synthesis processes have been performed via a molten salt method, and scanning electron microscopy, scanning probe microscopy, and inductively coupled plasma mass spectroscopy were used to characterize the synthesized K1/2Na1/2NbO3 or NaNbO3 templates.

  6. Marketingový mix Restaurace Na chalupě

    OpenAIRE

    Kubíková, Martina

    2013-01-01

    Bakalářská práce se zaměřuje na rozbor marketingu a především marketingového mixu. Tedy na známé definice marketingu, marketingová prostředí a rozbor marketingového mixu, kde jsou zmapovány všechny jeho části (Produkt, Cena, Distribuce, Propagace, Fyzický důkaz, Lidé, Procesy). Z teoretických poznatků, které byly zjištěny v odborné literatuře, je vypracována praktická část. Zde je rozebrán marketingový mix Restaurace Na chalupě a zároveň tak i porovnání dvou provozovatelů, kteří se zde vystří...

  7. Co-intercalation of Mg(2+) and Na(+) in Na(0.69)Fe2(CN)6 as a High-Voltage Cathode for Magnesium Batteries.

    Science.gov (United States)

    Kim, Dong-Min; Kim, Youngjin; Arumugam, Durairaj; Woo, Sang Won; Jo, Yong Nam; Park, Min-Sik; Kim, Young-Jun; Choi, Nam-Soon; Lee, Kyu Tae

    2016-04-06

    Thanks to the advantages of low cost and good safety, magnesium metal batteries get the limelight as substituent for lithium ion batteries. However, the energy density of state-of-the-art magnesium batteries is not high enough because of their low operating potential; thus, it is necessary to improve the energy density by developing new high-voltage cathode materials. In this study, nanosized Berlin green Fe2(CN)6 and Prussian blue Na(0.69)Fe2(CN)6 are compared as high-voltage cathode materials for magnesium batteries. Interestingly, while Mg(2+) ions cannot be intercalated in Fe2(CN)6, Na(0.69)Fe2(CN)6 shows reversible intercalation and deintercalation of Mg(2+) ions, although they have the same crystal structure except for the presence of Na(+) ions. This phenomenon is attributed to the fact that Mg(2+) ions are more stable in Na(+)-containing Na(0.69)Fe2(CN)6 than in Na(+)-free Fe2(CN)6, indicating Na(+) ions in Na(0.69)Fe2(CN)6 plays a crucial role in stabilizing Mg(2+) ions. Na(0.69)Fe2(CN)6 delivers reversible capacity of approximately 70 mA h g(-1) at 3.0 V vs Mg/Mg(2+) and shows stable cycle performance over 35 cycles. Therefore, Prussian blue analogues are promising structures for high-voltage cathode materials in Mg batteries. Furthermore, this co-intercalation effect suggests new avenues for the development of cathode materials in hybrid magnesium batteries that use both Mg(2+) and Na(+) ions as charge carriers.

  8. Efeito do corte como dano mecânico na qualidade e na fisiologia de mamões 'golden'

    Directory of Open Access Journals (Sweden)

    Jaqueline Visioni Tezotto

    2011-10-01

    Full Text Available A redução na qualidade pós-colheita do mamão deve-se em grande parte aos danos mecânicos, especialmente àqueles do tipo corte. O objetivo deste trabalho foi reproduzir este dano mecânico e avaliar os efeitos do número de cortes na qualidade e na fisiologia pós-colheita de mamões 'Golden'. Os cortes foram obtidos com o uso de uma lâmina de aço de 30 mm de comprimento e 5 mm de profundidade. Os tratamentos consistiram na reprodução de 1 a 4 cortes na região mediana dos frutos. Mamões sem cortes foram utilizados como controle. Após a reprodução dos danos, os frutos foram armazenados em câmara a 22ºC e 80-90% de UR por 10 dias. As análises de qualidade foram realizadas a cada dois dias, e as fisiológicas, diariamente. Os resultados demonstraram que a firmeza, o teor de sólidos solúveis e de ácido ascórbico, a atividade respiratória e a produção de etileno foram influenciados pelo número de cortes, de forma que a perda de qualidade dos frutos foi diretamente proporcional ao número de cortes.

  9. Hydrothermal crystallization of Na2Ti6O13, Na2Ti3O7, and Na16Ti10O28 in the NaOH-TiO2-H2O system at a temperature of 500 deg. C and a pressure of 0.1 GPa: The structural mechanism of self-assembly of titanates from suprapolyhedral clusters

    International Nuclear Information System (INIS)

    Hyushin, G. D.

    2006-01-01

    An increase in the NaOH concentration in the NaOH-TiO 2 (rutile)-H 2 O system at a temperature of 500 deg. C and a pressure of 0.1 GPa leads to the crystallization R-TiO 2 + Na 2 Ti 6 O 13 → Na 2 Ti 3 O 7 → Na 16 Ti 10 O 28 . Crystals of the Na 2 Ti 6 O 13 titanate (space group C2/m) have the three-dimensional framework structure Ti 6 O 13 . The structure of the Na 2 Ti 3 O 7 titanate (space group P2 1 /m) contains the two-dimensional layers Ti 3 O 7 . The structure of the Na 16 Ti 10 O 28 titanate (space group P-1) is composed of the isolated ten-polyhedron cluster precursors Ti 10 O 28 . In all the structures, the titanium atoms have an octahedral coordination (MTiO 6 ). The matrix self-assembly of the Na 2 Ti 6 O 13 and Na 2 Ti 3 O 7 (Na 4 Ti 6 O 14 ) crystal structures from Na 4 M 12 invariant precursors is modeled. These precursors are clusters consisting of twelve M polyhedra linked through the edges. It is demonstrated that the structurally rigid precursors Na 4 M 12 control all processes of the subsequent evolution of the crystal-forming titanate clusters. The specific features of the self-assembly of the Na 2 Ti 3 O 7 structure that result from the additional incorporation of twice the number of sodium atoms into the composition of the high-level clusters are considered

  10. NA48: Wiring up for Change

    CERN Multimedia

    2001-01-01

    The NA48 Collaboration is rebuilding its drift chambers ready for the experiment to start up again this coming July. An intricate task involving the soldering of over 24,000 wires! The future of the NA48 experiment is coming right down to the wire, that is, the wires which the Collaboration is installing in the clean room of Hall 887 on the Prévessin site. Six days a week, technicians are working in shifts to rebuild the experiment's drift chambers. The original chambers were damaged when a section of a vacuum tube imploded at the end of 1999. A year ago, CERN gave the green light for this essential part of the spectrometer to be rebuilt, so the NA48 experiment, which studies CP violation (see box), still has a bright future ahead of it. Three years of data-taking ahead The NA48 experiment aims to penetrate the secrets of CP (Charge Parity) violation. Charge and parity are two parameters which distinguish a particle from an antiparticle. In other words, an electron possesses a negative electric ...

  11. Impact of childhood stress on psychopathology Impacto de estresse na infância na psicopatologia

    Directory of Open Access Journals (Sweden)

    Elisa Brietzke

    2012-12-01

    Full Text Available OBJECTIVE: Advances in our knowledge of mental disorder (MD genetics have contributed to a better understanding of their pathophysiology. Nonetheless, several questions and doubts persist. Recent studies have focused on environmental influences in the development of MDs, and the advent of neuroscientific methodologies has provided new perspectives. Early life events, such as childhood stress, may affect neurodevelopment through mechanisms such as gene-environment interactions and epigenetic regulation, thus leading to diseases in adulthood. The aim of this paper is to review the evidence regarding the role of the environment, particularly childhood stress, in the pathophysiology of MD. METHODOLOGY: We reviewed articles that evaluated environmental influences, with a particular focus on childhood trauma, brain morphology, cognitive functions, and the development of psychopathology and MD. RESULTS AND CONCLUSION: MRI studies have shown that exposure to trauma at an early age can result in several neurostructural changes, such as the reduction of the hippocampus and corpus callosum. Cognitive performance and functioning are also altered in this population. Finally, childhood stress is related to an increased risk of developing MD such as depression, bipolar disorder, schizophrenia and substance abuse. We conclude that there is robust evidence of the role of the environment, specifically adverse childhood experiences, in various aspects of MD.OBJETIVO: Avanços no conhecimento da genética dos transtornos mentais (TM contribuíram para um melhor entendimento de suas bases fisiopatológicas. No entanto, dúvidas e questões ainda persistem. Estudos recentes têm se concentrado nas influências do ambiente no desenvolvimento de TM, e o advento de metodologias neurocientíficas oferece novas perspectivas. Eventos precoces de vida, como estresse na infância, podem ser capazes de alterar o neurodesenvolvimento através de mecanismos como intera

  12. Oxidation of ethanol on NaX zeolite modified with transition metals

    Science.gov (United States)

    Mirzai, J. I.; Nadirov, P. A.; Velieva, A. D.; Muradkhanli, V. G.

    2017-06-01

    NaLaX, NaX + Co, and NaPdX catalysts are synthesized by modification of NaX zeolite with transition metals (La, Co, Pd). The activity of the prepared materials in catalytic ethanol oxidation is studied in the temperature range of 423-723 K. It is shown that NaPdX and NaX + Co accelerate the reactions of partial and complete oxidation of ethanol as the temperature rises. NaLaX accelerates both intramolecular and intermolecular dehydration of alcohol. It is shown that the NaPdX (1.0% Pd) sample has the highest activity in the complete oxidation of alcohol with the formation of CO2.

  13. Non-preferential fuelling of the Na(+)/K(+)-ATPase pump.

    Science.gov (United States)

    Fernández-Moncada, Ignacio; Barros, L Felipe

    2014-06-15

    There is abundant evidence that glycolysis and the Na(+)/K(+)-ATPase pump are functionally coupled, and it is thought that the nature of the coupling is energetic, with glycolysis providing the ATP that fuels the pump. This notion has been instrumental to current models of brain energy metabolism. However, structural and biophysical considerations suggest that the pump should also have access to mitochondrial ATP, which is much more abundant. In the present study, we have investigated the source of ATP that fuels the Na(+) pump in astrocytes, taking advantage of the high temporal resolution of recently available FRET nanosensors for glucose, lactate and ATP. The activity of the Na(+) pump was assessed in parallel with the Na(+)-sensitive dye SBFI AM (Na(+)-binding benzofuran isophthalate acetoxymethyl ester). OXPHOS (oxidative phosphorylation) inhibition resulted in bulk ATP depletion and a 5-fold stimulation of glycolytic flux, in spite of which Na(+) pumping was inhibited by 90%. Mathematical modelling of ATP dynamics showed that the observed pump failure is inconsistent with preferential fuelling of the Na(+) pump by glycolytic ATP. We conclude that the nature of the functional coupling between the Na(+) pump and the glycolytic machinery is not energetic and that the pump is mainly fuelled by mitochondrial ATP.

  14. Atletismo na escola : realidade?

    OpenAIRE

    Sampaio, Alessandro Oliveira de

    2012-01-01

    O correr, saltar, lançar e arremessar são elementos básicos do atletismo, sendo fundamentais para o ser humano, devido ao favorecimento do desenvolvimento físico e motor. Sendo um dos conteúdos principais do desporto e da educação física escolar, foi realizado um estudo relacionado à prática do atletismo na escola, na qual o objetivo desta pesquisa foi verificar se entre os professores de educação física da rede pública de ensino fundamental de 5ª a 8ª séries, da cidade satélite de Samambaia ...

  15. Influence of NaCl and NaHCO/sub 3/ on reduction of phytic acid in red kidney bean

    International Nuclear Information System (INIS)

    Shahnawaz, M.; Khan, T.U.

    2007-01-01

    Influence of sodium chloride (NaCI) and sodium bicarbonate (NaHCO/sub 3/) was studied on phytic acid in Red kidney bean (phaseolus sp). Two varieties of Red Kidney bean VI (Orakzai Korkha) and V2 (Kurram Korkha) were obtained from NWFP Agriculture University, Peshawar. The amount of phytic acid in V1 and V2 of Red kidney bean was 10 mg and 9.80 mg, respectively. Red kidney-bean flour soaked for 6 and 12 hrs. in water and in pH4 and 6 solutions has significantly reduced (70%) amount of phytic acid. Solution of pH6 was found most effective, while pH4 and water was less effective in lowering the phytic acid in Red kidney bean. Mixed food additives (1% NaCI + 2% NaHCO/sub 3/) in water, and pH4 and 6 solutions, reduced the level of phytic acid in Red kidney bean to 40%, 54% and 58% for 6 hrs, and 50%, 57% and 70% for 12 hrs. in respective solutions. Results revealed that soaking Red kidney bean flour in pH6 solution with the presence of NaCI and NaHCO/sub 3/, the action of phytase enzyme was well activated to hydrolyze phytic acid. It has been observed that soaking of flour in the respective solutions is a simple inexpensive method of lowering phytic acid in bean. The treatment with such a sophisticated combination of food additives will improve the nutritional status of Red kidney bean, which is used in many food products. (author)

  16. Na2SO4-based solid electrolytes for SOx sensors

    DEFF Research Database (Denmark)

    Rao, N.; Schoonman, J.; Toft Sørensen, O.

    1992-01-01

    on the phases present and the structure of the specimens. From a point of view of practical application as SOx sensor material, the Na2SO4 + 5 mol% Y2(SO4)3 + Na2WO4 and Na2SO4+ 4 mol% La2(SO4)3 + Na2WO4 materials are better than undoped Na2SO4 because of their higher conductivity, and absence of a phase...

  17. Kinetin Reversal of NaCl Effects

    Science.gov (United States)

    Katz, Adriana; Dehan, Klara; Itai, Chanan

    1978-01-01

    Leaf discs of Nicotiana rustica L. were floated on NaCl in the presence of kinetin or abscisic acid. On the 5th day 14CO2 fixation, [3H]leucine incorporation, stomatal conductance, and chlorophyll content were determined. Kinetin either partially or completely reversed the inhibitory effects of NaCl while ABA had no effect. PMID:16660618

  18. Combined Effects of Boron and NaCl on Wheat Seedlings

    Directory of Open Access Journals (Sweden)

    ZHEN Mei-nan

    2015-08-01

    Full Text Available To investigate the combined effects of boron(Band NaCl on the growth of wheat, a pot experiment was conducted using wheat (Triticum aestivum Linn.seedlings. Boron concentrations of culture medium were set as 0, 50 mg·kg-1 and 100 mg·kg-1, and NaCl concentrations were 0, 1 g·kg-1 and 2 g·kg-1. The results showed that both boron and NaCl could significantly inhibit wheat growth. At 50 mg B·kg-1, NaCl aggravated growth inhibition caused by boron. At 100 mg B·kg-1, however, NaCl alleviated the inhibition caused by boron. The combined stress of boron and NaCl significantly increased the root to shoot ratio of wheat. NaCl inhibited the uptake of boron by wheat. It suggests that under severe boron stress, NaCl is able to alleviate boron toxicity in wheat by increasing root to shoot ratio and reducing boron uptake.

  19. An enhancement to the NA4 gear vibration diagnostic parameter

    Science.gov (United States)

    Decker, Harry J.; Handschuh, Robert F.; Zakrajsek, James J.

    1994-01-01

    A new vibration diagnostic parameter for health monitoring of gears, NA4*, is proposed and tested. A recently developed gear vibration diagnostic parameter NA4 outperformed other fault detection methods at indicating the start and initial progression of damage. However, in some cases, as the damage progressed, the sensitivity of the NA4 and FM4 parameters tended to decrease and no longer indicated damage. A new parameter, NA4* was developed by enhancing NA4 to improve the trending of the parameter. This allows for the indication of damage both at initiation and also as the damage progresses. The NA4* parameter was