WorldWideScience

Sample records for zvyseny vykon reaktoru

  1. Virtuální prohlídka staveniště termojaderného reaktoru aneb Tour de ITER

    Czech Academy of Sciences Publication Activity Database

    Řípa, Milan

    Únor (2017) ISSN 2464-7888 Institutional support: RVO:61389021 Keywords : fusion * ITER * tokamak * virtual * 2D * 3D * dron Subject RIV: BL - Plasma and Gas Discharge Physics OBOR OECD: Fluids and plasma physics (including surface physics) http://www.3pol.cz/cz/rubriky/jaderna-fyzika-a-energetika/1977-virtualni-prohlidka-staveniste-termojaderneho-reaktoru-aneb-tour-de-iter

  2. Mezivýměník tepla primárního okruhu reaktoru ESFR

    OpenAIRE

    Švihel, Miroslav

    2012-01-01

    Práce je zaměřena především na návrh mezivýměníku tepla primárního okruhu reaktoru ESFR. Výměník je počítán tepelně, hydraulicky i pevnostně a závěrem je zpracována část výkresové dokumentace. Jsou navrhnuty základní rozměry trubkového svazku a nádoby výměníku. Je zde obsažen i přehled koncepcí výměníků a doposud použitých typů mezivýměníku na jaderných elektrárnách s rychlými reaktory. Uvedeny jsou zde i základní parametry projektu ESFR a zhodnocena bezpečnost a provozní spolehlivost výměník...

  3. Neutron magnetic scattering experiments performed by VIKRA group at the RA reactor in Vinca; Eksperimenti grupe VIKRA na reaktoru RA u Vinci sa rasejanjem neutrona na magnetnim materijalima

    Energy Technology Data Exchange (ETDEWEB)

    Kranicki, S; Rzany, H; Wanic, A [Institute of Nuclear Physics, Krakov (Poland); Szytula, A [Jagiellonian University, Krakov (Poland); Todorovic, J; Dimitrijevic, Z; Radenkovic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1978-05-15

    A short communication about investigations of magnetic materials by means of the neutron magnetic scattering performed by Polish-Yugoslav group VIKRA (Vinca-Krakov) at the RA reactor in Vinca in the period 1962-1977 will be presented. In the field of neutron inelastic scattering information about magnetic interactions (exchange integrals) and their temperature behaviour in such substances as Fe{sub 7}S{sub 8}, {alpha}-Fe{sub 2}O{sub 3}, CR{sub 2}O{sub 3}, {alpha}-Co, Cu{sub 2}MnAl and Mn{sub 1.88}Cr{sub 0.12}Sb was obtained by measuring magnon dispersion relations. In the field of neutron elastic scattering valuable results concerning crystallographic and magnetic structures of oxyhydroxides, several Heusler alloys and intermetallic compounds of 3d metals (for instance of NiMnGe, CoMnSi) were obtained. A short description of the KSN spectrometer used in all experiments will also be given. (author) Dato je kratko saopstenje o istrazivanjima magnetnih materijala magnetnim neutronskim rasejanjem izvrsenim od strane poljsko-jugoslovenske grupe VIKRA (Vinca-Krakov) na reaktoru RA u Vinci u periodu od 1962-1977. U oblasti neelasticnog rasejanja neutrona, obavestenja o magnetnim uzajamnim dejstvima (integralima izmene) i njihovim temperaturskim ponasanjima su dobijeni merenjem disperzione relacije magnona u takvim materijalima kao sto su Fe{sub 7}S{sub 8}, {alpha}-Fe{sub 2}O{sub 3}, CR{sub 2}O{sub 3}, {alpha}-Co, Cu{sub 2}MnAl and Mn{sub 1.88}Cr{sub 0.12}Sb. U oblasti neutronskog elasticnog rasejanja dobijeni su korisni rezultati o kristalografskim i magnetnim strukturama oksihidroksida gvozdja, niza Heuslerovih legura i intermetalnih jedinjenja 3d metala (napr. NiMnGe, Co,MnSi). Dat je kratak opis KSN spektrometra upotrebljenog u svim ovim eksperimentima. (author)

  4. Task 08/41, Low temperature loop at the RA reactor, Review I of materials planned for irradiation within the five-year plan of nuclear power development in Federal Peoples Republic of Yugoslavia; Zadatak 08/41, Niskotemperaturna petlja u reaktoru 'A', Pregled I materijala predvidjenih za ozracivanje petogodisnjim planom razvoja nuklearne energije FNRJ

    Energy Technology Data Exchange (ETDEWEB)

    Milenkovic, S; Milasin, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    For the purpose of designing the low-temperature loop at the RA reactor, a list of materials that would be irradiated in the reactor was made. This review includes materials which should be irradiated in for isotope production and materials to be irradiated for research and testing purposes. The neutron flux needed for materials testing should be much higher than presently available neutron flux of 10{sup 12} n/cm{sup 2} sec. [Serbo-Croat] Za potrebe projektovanja niskotemperaturne petlje na reaktoru RA nacinjen je pregled materijala za ozracivanje u reaktoru. Pregled sadrzi materijale za ozracivanje u cilju proizvodnje izotopa i materijale za specijalna ozracivanja u cilju ispitivanja materijala. Za ispitivanje materijala potreban bi bio fluks neutron koji je znatno veci od raspolozivog fluksa od 10{sup 12} n/cm{sup 2} sec.

  5. Devices for irradiation of materials in the fast neutron flux at the RA heavy water reactor in Vinca; Uredjaji za ozracivanje materijala u fluksu brzih neutrona na teskovodnom reaktoru RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-07-01

    Full text: This paper covers the concept, design description and problems of constructing special experimental devices at the RA reactor in Vinca. These devices were used for irradiation of construction materials (graphite, Mg and Al oxides, steel and zircaloy) in the integral fast neutron flux of 2 x 10{sup 20} n/cm{sup 2}. Temperature of samples cooled by heavy water circulating through the hollow uranium fuel elements was measured by thermocouples. Construction of the device, preparation of samples, related flux measurements as well as irradiation were done in cooperation with the nuclear center in Saclay, France. Brief review of the experiences gained in using these experimental spaces at the RA reactor as well as problems of transporting the irradiated capsules from Vinca to France is included. [Serbo-Croat] Pun tekst: Rad obuhvata koncepciju, tehnicki opis i probleme realizacije specijalnih eksperimentalnih uredjaja u reaktoru RA u Vinci, u kojima je tokom 1962. godine izvrseno, na temperaturama ispod 100 deg C, ozracivanje konstrukcionih materijala (grafita, Mg i Al-oksida, celika i cirkaloja) u integralnom fluksu brzih neutrona vrednosti 2 x 10{sup 20} n/cm{sup 2}. Temperatura uzoraka hladjenih teskom vodom, koja protice kroz suplje uranske elemente, merena je termoparovima. Realizacija uredjaja, priprema uzoraka, odgovarajuca merenja fluksa kao i sama ozracivanja vrsena su u saradnji sa Nuklearnim centrom u Saclay-u, Francuska. Dat je kraci pregled iskustava iz eksploatacije ovih novih eksperimentalnih prostora u reaktoru RA, kao i neki problemi vezani za transport aktivnih kapsula sa uzorcima od Vince do Saclay-a (author)

  6. Control of radiation fields at the RA reactor (Radiological data relevant for the period when irregularities on the fuel elements were observed), Part 2, Annex 1; Kontrola radijacionih polja na reaktoru RA (Neki podaci relevantni za ocenu radijacione situacije na reaktoru za period u kome su otkrivene neregularnosti na reaktorskom gorivu), Prilog 1, Deo 2

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-10-15

    period in question to prove the above conclusion. [Serbo-Croat] U sklopu programa mera zastite od zracenja u radnoj sredini na reaktoru RA vrsi se kontrola i merenje osnovnih karakteristika radijacionih polja: nivoi gama zracenja na karaktoristicnim tackama reaktorskih sistema, nivoi gamma zracenja i neutrona u pojedinim radnim i tehnoloskim prostorijama, koncentracija radioaktivnih aerosola i sadrzaj radioaktivnih gasova u vazduhu radnih i tehnoloskih prostorija, nivoi kontaminacije radnih povrsina, alata, opreme i odece zaposlenih, kontrola individualnog izlaganja zracenju, evidencija i kontrola unutrasnjeg i spoljasnjeg manipulisanja kontaminiranim i aktiviranim predmetima, aktiviranim materijalima, radioaktivnim izvorima i radioaktivnim otpadnim materijalom. Svi podaci o merenjima karakteristika radijacionih polja registruju se u dnevnicima koje vodi dezurno osoblje i u periodicnim izvestajima. Uvidom u pomenute dnevnike i izvestaje, nisu uocena nikakva znacajna odstupanja u nivoima zracenja i merenim karakteristikama radijacionih polja za period februar-mart u odnosu na vrednosti iz prethodnih godina. U trenutku kada su otkrivene neregularnosti na gorivnim elementima iz poslednje sarze goriva u reaktoru, krajem marta ove godine, postavilo se pitanje da li doslo do isticanja fisionih produkata iz nekog elementa. Zahvaljujuci iskustvu stecenom prilikom prvog i do sada jedinog prskanja kosuljice gorivnog elementa, pre oko devet godina, moglo se sa visokim stepenom sigurnosti tvrditi da do toga nije doslo. Da je doslo do isticanja fisionih produkata znacajno bi se povecali nivoi zracenja na karakteristicnim tackama reaktorskih sistema, i u radnoj sredini povecao bi se i relativni sadrzaj fisionih produkata u rashadnom mediju, moguce bi bilo registrovati sveze fisione produkte kao sto je {sup 131} I, u vecim kolicinama. Medjutim, nista od toga nije registrovano. Moze se zakljuciti da nijedan gorini elemenat nije procurio, i da se sve standardne operacije manipulisanja

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-15

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

  8. Neutron converter at reactor RB; Konvertor neutrona na reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P; Sotic, P; Ninkovic, M; Pesic, M [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1977-07-01

    A neutron converter at Reactor RB in the 'Boris Kidric' Institute of Nuclear Sciences - Vinca has been constructed. Preliminary measurements have been shown that the converted neutron spectrum is very similar to the fission neutron spectrum. For the same integral reactor power, the measured neutron radiation dose has been for about ten times larger with the neutron converter. The neutron converter offers wide possibilities, as in investigations in the reactor physics, where the fission neutron spectra have been required, as well as in the field of neutron dosimetry and biological irradiations (author)

  9. Parní generátor reaktoru ESFR

    OpenAIRE

    Bátěk, David

    2012-01-01

    Tato diplomová práce se zabývá parním generátorem pro reaktory ESFR (Evropský Rychlý Sodíkem Chlazený Reaktor), jenž je vyhříván tekutým sodíkem. V úvodních kapitolách jsou teoretické informace o parametrech ESFR a porovnání s výměníky tepla v jaderných elektrárnách pracujících na stejném principu (sodík jako chladivo). Následuje návrhová část, kam patří úvod do problematiky výpočtu, volba materiálu a koncepce výměníku a samotná výpočtová část, která zahrnuje tepelný, hydraulický a pevnostní ...

  10. Vliv hydrodynamiky na HDS testy ve zkrápěném reaktoru

    OpenAIRE

    Tukač, V.

    2012-01-01

    The study was fosussed on identification of flow parameters of gas and liquid phases during hydrodesulphurization in laboratory trickle bed reactor in order to minimize transfer phenomena effects on experimental measurement.

  11. Hydrogenace styrenu v pilotním zkrápěném reaktoru

    Czech Academy of Sciences Publication Activity Database

    Šimíčková, M.; Tukač, V.; Chyba, V.; Lederer, J.; Kolena, J.; Šimek, J.; Hanika, Jiří

    2005-01-01

    Roč. 1, - (2005), 117 /6P10/ ISSN 1336-7242. [Zjazd chemických spoločností /57./. 04.09.2005-08.09.2005, Tatranské Matliare] Institutional research plan: CEZ:AV0Z40720504 Keywords : styrene * hydrogenation * trickle bed reactor Subject RIV: CI - Industrial Chemistry, Chemical Engineering

  12. 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.

  13. Fire damp gas in a heavy water reactor; Praskavi gas u teskovodnom reaktoru

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, V D [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Yugoslavia)

    1963-07-01

    This document describes the process of fire damp gas creation in the reactor core and dependence of the gas percentage on the temperature, i.e. reactor power. It contains a detailed plan for measuring the the percent of fire damp gas at the RA reactor: before start-up, after longer shut-down periods, immediately after safety shutdown, periodically during operation campaign.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

    This report includes results of the following measurements performed at the RA reactor: thermal neutron flux in the experimental channels, epithermal and fast neutron flux, neutron flux in the biological shield, neutron flux distribution in the reactor cell.

  15. Stochastic processes analysis in nuclear reactor using ARMA models; Analiza stohastichkih procesa u nuklearnom reaktoru korishcjenjem ARMA modela

    Energy Technology Data Exchange (ETDEWEB)

    Zavaljevski, N [Institute of Nuclear Sciences Boris Kidric VINCA, Belgrade (Yugoslavia)

    1990-07-01

    The analysis of ARMA model derived from general stochastic state equations of nuclear reactor is given. The dependence of ARMA model parameters on the main physical characteristics of RB nuclear reactor in Vinca is presented. Preliminary identification results are presented, observed discrepancies between theory and experiment are explained and the possibilities of identification improvement are anticipated. (author)

  16. Contribution to solving the problem of neutron thermalization in heterogeneous reactor; Prilog resavanju problema termalizacije neutron u heterognom reaktoru

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1963-12-15

    A method for calculating of neutron termalization in heterogeneous rector core was developed. It is more precise than the diffusion method but more complcated. Concerning accuracy it is comparable to non-diffusion methods. Sonce the approach was analytical need for powerful computer is avoided and the description of physical phenomena is more transparent. Convergence is satsfactory. Constraints of the proposed method are: low neutron absorption in the moderator, negligible slowing down in the fuel, and big lattice pitch. The method is applicable for heavy water and graphite moderator systems. Based on the application of this method, procedures were developed for calculating thermal utilzation and neutron temperature. Since 1/v dependence of cross sections is not estimated this metof could be used for long-term reactivity changes.

  17. Coupled fast-thermal system at the RB, masters thesis; Spregnuti brzo-termicki sistem na reaktoru RB, magistarski rad

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1984-05-15

    Coupled fast-thermal system at the RB reactor was formed owing to availability of highly enriched fuel. This paper deals with reactor parameters calculations and measurements of coupled core taking into account safety constraints. Validity of applied calculation methods was confirmed. The following parameters were analyzed: critical height of the core; reactivity dependent on heavy water level in the core; fast neutron spectrum in the fast region channel; spatial distribution of thermal. epithermal and fat neutrons in the fast region channel; reactivity of safety rods; neutron and gamma absorption doses in the center of the coupled core.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-07-01

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

  19. Safety shutdowns and failures of the RA reactor equipment; Sigurnosna zaustavljanja i kvarovi opreme na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-07-01

    This report is an attempt of statistical analysis of the failures occurred during RA reactor operation. A list of failures occurred on the RA equipment during 1965 is included. Failures were related to the following systems: dosimetry system (22%), safety and control system (7%), heavy water system (2%), technical water (4%), helium system (2%), measuring instruments (30%), transport, ventilation, power supply systems (32%). A review of safety shutdowns from 1962 to 1966 is included as well, as a comparison with three similar reactors. Although the number of events used for statistical analysis was not adequate, it has been concluded that RA reactor operation was stable and reliable.

  20. 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.

  1. New neutron and gamma dosimetry equipment at the RB reactor; Nova merna neutronska i gama dozimetrijska oprema na reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-07-15

    In the frame of bilateral cooperation between Germany and Yugoslavia, complete control, safety and dosimetry equipment of the shut-down SNEAK reactor was donated to Vinca Institute and transported to be installed at the RB reactor. This report contains detailed description of instrumentation components including detectors, electronic components and electronic circuits. Experimental data which verified correct functioning of the installed devices are part of this document. The objective of the RB reactor staff is to achieve new safety and dosimetry system in order to improve the reliability and availability of the RB reactor for future experiments.

  2. Engineering documentation of the GM counter at the RB reactor; Tehnicka dokumentacija GM brojaca na reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

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

    1986-07-01

    A GM counting device was completed. It is meant for absolute and relative measurements of beta and gamma activities of the irradiated samples as well as for determining the radiation transmission properties of the materials. This report shows technical and operation characteristics of the device. Realizovan je GM brojacki uredjaj koji je namenjen za apsolutna i relativan merenja beta i gama akrivnosti ozracenih uzoraka kao i za odredjivanje transmisionih karakteristika materijala za ova zracenja. U radu su prokazane tehnicke i radne karakteristike uredjaja. (author)

  3. Feasibility study of applying reactor oscillator phase method at the RB reactor; Razmatranje mogucnosti primene fazne metode reaktorskog oscilatora na reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Kocic, A; Markovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    This paper decsribes the principles of amplitude and phase methods for applying reactor oscillator; experimental procedure and choice of optimum parameters for usractor oscillator at the RB reactor, dependent on the values of absorption properties of moderator and construction materials. Short description of the oscillator and the electronic equipment is included.

  4. Design project of the experimental device for studying the uranium Creep in the reactor; Predprojekat eksperimentalnog uredjaja za ispitivanje CREEP-a urana u reaktoru

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Odeljenje za reaktorsku eksperimentalnu tehniku, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    The objective of this task was constructing a device for creep testing of uranium, i.e permanent deformation of the irradiated fuel. Deformation results from the influence of thermal neutron flux, temperature, time of irradiation, mechanical stress. This describes two possible technical solutions experimental device for creep testing in the vertical experimental channel and in the horizontal experimental channel of the RA reactor. In addition to the design details, the report covers calculations of heat generation, antireactivity, activation of the materials of the constructed experimental loop, mechanical calculations as well as description of measurements and regulation of the uranium sample temperature.

  5. 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}.

  6. Design project of the experimental facility for testing uranium creep in the reactor; Predprojekat eksperimentalnog uredjaja za ispitivanje CREEP-a urana u reaktoru

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-12-15

    This report contains the design for constructing the experimental device for testing metal uranium creep in the RA reactor core under defined neutron flux conditions, temperature, mechanical loads and time of irradiation. This device will be placed in one of the experimental channels in the core. This report contains physical, thermal and mechanical calculations and engineering drawings of the device.

  7. Calorimeter measurements of absorbed doses at the heavy water enriched uranium reactor; Kalorimetrijska merenja apsorbovanih doza u reaktoru na tesku vodu i obogaceni uran

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, V [Institute of Nuclear Sciences Boris Kidric, Odeljenje za radijacionu hemiju, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Application of calorimetry measurements of absorbed doses was imposed by the need of good knowledge of the absorbed dose values in the reactor experimental channels. Other methods are considered less reliable. The work was done in two phases: calorimetry measurements at lower reactor power (13-80 kW) by isothermal calorimeter, and differential calorimeter constructions for measurements at higher power levels (up to 1 MW). This report includes the following four annexes, papers: Isothermal calorimeter for reactor radiation monitoring, to be published; Calorimeter dosimetry of reactor radiation, presented at the Symposium about nuclear fuel held in april 1961; Radiation dosimetry of the reactor RA at Vinca, published in the Bull. Inst. Nucl. Sci. 1961; Differential calorimeter for reactor radiation dosimetry.

  8. Measurement of spectrum at the experimental 6.5 MW reactor in Vinca; Merenje spektra na eksperimentalnom 6,5 MW reaktoru u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Berovic, N; Boreli, F; Aleksic, N; Dragin, R [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1961-07-01

    Since RA reactor is supplied with horizontal experimental channels which lead directly to the core fast neutron spectrum in the channel does not differ much from the neutron spectrum in the core. Spectrum was measured by 'telescope' for detecting scattered protons. Measuring procedure together with the measured spectrum are presented in this paper.

  9. Analysis of accident caused by temperature increase at the RA reactor in Vinca; Analiza udesa usled povisenja temperature na reaktoru RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-06-15

    The objective of this work was to determine the maximum time interval without accident due to mechanical failures. The following accidents caused by mechanical failures are taken into account: loss of moderator flow, moderator leaking with or without circulation, and accidents caused by removal of fuel channels from the reactor vessel. Obtained numerical and experimental results are presented. Experimental device installed at the reactor was used for verification of calculation results. The analysis was done for the most damaging conditions and thus the obtained results represent the lowest boundary values. [Serbo-Croat] Rad je baziran na pronalazenju maksimalnih vremena pri kojima i pored mehanickih kvarova nece doci do udesa. Posmatrani su slucajevi: prestanak cirkulacije moderatora, curenje moderatora uz i bez postojece cirkulacije, kao i udesi pri vadjenju tehnoloskih kanala iz reaktorskog suda. Dobijeni su rezultati numerickom i eksperimentalnom metodom. Eksperimentalna aparatura je postavljena da bi se dobila potvrda numerickih rezultata. U radu se vodilo racuna da se uvek analiziraju najnepovoljniji slucajevi pa su zato i dobijeni rezultati donje granice resenja (author)

  10. Measurement of control rods efficiency at the RB reactor by pulse method; Merenje efikasnosti kontrolnih sipki u reaktoru RB impulsnom metodom

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    Pulse method was applied for measuring the efficiency of control rods at the RB reactor. This paper describes the theory of experiment, experimental procedure applied and results obtained. Results are considered to be useful for safety analysis. it was found that the influence of delayed neutrons is rather small and could be neglected in estimation of rods efficiency.

  11. New start-up channels and multichannel analyzer at the RB reactor; Novi start-up kanali i videkanalni analizator na reaktoru Rb

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-01-15

    New start-up channels and a multichannel analyzer were purchased in 1977 for the RB reactor. Both start-up channels contain BF{sub 3} neutron detectors, preamplifier, amplifier, single-channel analyzer, scaler, ratemeter, control unit, recording instrument. This document contains detailed technical description of these devices as well as characteristics of the multichannel analyzer which is being tested and will be used for measuring irradiation in the vicinity of the reactor.

  12. Otěr minerálních katalyzátorů ve fluidním zplyňovacím reaktoru

    Czech Academy of Sciences Publication Activity Database

    Hartman, Miloslav; Svoboda, Karel; Pohořelý, Michael; Šyc, Michal

    2012-01-01

    Roč. 106, č. 9 (2012), s. 844-846 ISSN 0009-2770 R&D Projects: GA AV ČR IAA400720701 Grant - others:RFCR(XE) CT2010-00009 Institutional support: RVO:67985858 Keywords : gasification of biomass * catalyst attrition * dolomites and limestones Subject RIV: CI - Industrial Chemistry, Chemical Engineering Impact factor: 0.453, year: 2012

  13. Spalování kukuřičné slámy v reaktoru s bublinovou fluidní vrstvou.

    Czech Academy of Sciences Publication Activity Database

    Durda, Tomáš; Moško, Jaroslav; Pohořelý, Michael; Svoboda, Karel; Zach, Boleslav; Šyc, Michal; Jeremiáš, Michal; Krausová, Aneta; Punčochář, Miroslav

    2016-01-01

    Roč. 8, č. 1 (2016), s. 29-38 ISSN 1804-2058 R&D Projects: GA TA ČR TA01020366 Institutional support: RVO:67985858 Keywords : fluidized bed * agricultural biomass * oxy- fuel combustion Subject RIV: DI - Air Pollution ; Quality http://paliva.vscht.cz/cz/archiv-clanku/detail/30

  14. Documents needed for obtaining the operation licence for the HERBE system at the RB reactor; Dokumentacija za dobijanje dozvole za rad sistema HERBE na reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M et al [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1989-10-15

    Documents included in this volume are needed for obtaining the operation licence for the coupled fast-thermal system HERBE constructed at the RB reactor. It contains the following chapters: description of the system; nuclear calculations; performed changes at the RB reactor; proofs about static and dynamic stability of the built construction; normal operation regime of HERBE; accident analysis; dosimetry data; additional instructions and regulations for reactor operation; program of start-up; program for testing the HERBE system.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-07-01

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

  16. Measurement of thermal conductivity of sintered UO{sub 2} in the reactor; Merenje toplotne provodljivosti sinterovanog UO{sub 2} u reaktoru

    Energy Technology Data Exchange (ETDEWEB)

    Katanic, J; Stevanovic, M [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1965-10-15

    Thermal conductivity is considered one of the fundamental properties of sintered UO{sub 2} fuel. Samples should be tested under real core conditions. This paper covers the methods and instruments for thermal conductivity measurement of UO{sub 2} samples in the reactor core, measurements outside the core under conditions similar to those in the core and outside the core after irradiation. Fuel samples are placed in capsules for irradiation in the reactor in-core loops.

  17. Report on participation of the operational dosimetry division in refurbishment of the RA reactor, Task 3.08/04-13; Podzadatak 3.08/04-13 Izvestaj o ucescu Odseka operativne dozimetrije RZ u remontnim radovima na Reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-12-15

    During the refurbishment of the RA reactor, from January to June 1963 the division of operational division had a very important role and comprehensive tasks. To enable safety of the staff it was necessary to provide protection clothes, personnel dosemeters; permanent monitoring of radiation doses; strict control of the procedures for completing the planned maintenance and repair operations to avoid contamination of the personnel and working space. The refurbishment activities described in this report are: removal of fuel from the core; refurbishment of the heavy water system; decontamination of the distillation equipment; repair of the gas system.

  18. Vliv periodicky modulovaného nástřiku na zádrž kapaliny a tlakovou ztrátu zkrápěného reaktoru

    Czech Academy of Sciences Publication Activity Database

    Tukač, V.; Hanika, Jiří

    2004-01-01

    Roč. 98, č. 9 (2004), s. 859-863 ISSN 0009-2770 Institutional research plan: CEZ:AV0Z4072921 Keywords : hold-up * trickle bed reactor * modulated feed Subject RIV: CI - Industrial Chemistry, Chemical Engineering Impact factor: 0.348, year: 2004

  19. Devices for irradiation of materials in the fast neutron flux at the RA heavy water reactor in Vinca; Uredjaji za ozracivanje materijala u fluksu brzih neutrona na teskovodnom reaktoru RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Full text: This paper covers the concept, technical description and problems of constructing special experimental facilities at the RA reactor in Vinca. During 1962, construction materials (graphite, Mg, Al-oxides, steel and Zircaloy) were irradiated in these facilities at temperatures below 100 deg C by the integral fast neutron flux of 2 10{sup 20} n/cm{sup 2}. Temperature of the samples cooled by heavy water circulating through hollow uranium elements was measured by thermocouples. Construction of the facility, sample preparation, related measurements of the flux and irradiation of the samples were done in cooperation with the Nuclear center in Saclay, France. A short review of the experiences in using the new experimental space at the RA reactor is given, together with some problems related to transport of radioactive capsules containing samples from Vinca to Saclay.

  20. Service for maintenance of electrical equipment at the RA reactor, Report for 1977 - Annex III; Prilog III - Rad sluzbe za odrzavanje elektroopreme na reaktoru RA u 1977. godini - Izvestaj

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-12-15

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

  1. Task 08/41, Low temperature loop at the RA reactor, Review IV - Maximum temperature values in the samples without forced cooling; Zadatak 08/41, Niskotemperaturna petlja u reaktoru 'RA', Pregled IV - Maksimalne temperature u uzorcima bez prinudnog hladjenja

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

    The quantity of heat generated in the sample was calculated in the Review III. In stationary regime the heat is transferred through the air layer between the sample and the wall of the channel to the heavy water of graphite. Certain value of maximum temperature t{sub 0} is achieved in the sample. The objective of this review is determination of this temperature. [Serbo-Croat] Kolicina toplote generisana u uzorku, izracunata u pregledu III, u ravnoteznom stanju odvodi se kroz vazdusni sloj izmedju uzorka i zida kanala na tesku vodu odnosno grafit, pri cemu se u uzorku dostize izvesna maksimalna temperatura t{sub 0}. Odredjivanje ove temperature je predmet ovog pregleda.

  2. Radioactive effluent sources and special system of channels on the RA Reactor at the Boris Kidric Institute; Izvori radioaktivnih efluenata i specijalna kanalizacija u reaktoru RA Instituta Boris Kidric

    Energy Technology Data Exchange (ETDEWEB)

    Bojovic, P; Gacinovic, O; Milosevic, M [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1964-10-15

    The paper describes the place of origin, composition and activity of radioactive effluents appearing in some reactor systems and special channels for carrying these effluents to disposal basins located outside the reactor building (author)

  3. New experimental space for irradiating samples by RA reactor fast neutron flux at temperatures up to 100 deg C; Novi eksperimentalni prostori namenjeni ozracivanju uzoraka u fluksu brzih neutrona na temperaturama do 100{sup 0} C na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Novakovic, M; Zecevic, V [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1961-07-01

    The objective of this paper is to present adaptation of the RA reactor which would enable samples irradiation by fast neutrons and describe new experimental possibilities. New experimental space was achieved using hollow fuel elements which have been reconstructed to enable placement of irradiation capsules inside the tube. This paper includes thermal analysis and describes problems related to operation, safety and radiation protection issues which arise from using reconstructed fuel elements.

  4. Optimal operating parameters of the reactor oscillator in the channel of 6.5/10 MW reactor; Odredjivanje optimalnih radnih tacaka za reaktorski oscilator u kanalu na reaktoru 6,5/10 MW

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    Operating conditions for the reactor oscillator in the central vertical experimental channel (VK5) in the RA reactor were studied during 1960. Channel VK5 was chosen because the sensitivity of the reactor is highest in this case. The central vertical experimental channel is placed in the center of the core and its bottom is placed 200 mm from the bottom of the reactor core. Diameter of the channel is is 110 mm and its length 5706 mm. During operation of the reactor oscillator with total modulation of the reactor power, it is very important to determine the oscillator operating point and the oscillation amplitude in such a way to avoid any change in reactor power level. Positive reactivity changes originating from oscillations of the samples should be compensated by the negative reactivity changes so that the effect should be nil. Operating points of the reactor oscillator are in the middle of the straight part of the figure showing the reactivity change dependent on the position of the absorber.

  5. Measurements at the RA Reactor related to the VISA-2 project - Part 2, Measurement of neutron flux in VISA-2 channels; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - II deo, Merenje fluksa neutrona u kanalima VISA - 2

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-15

    This report describes the task concerned with measurements of neutron flux in four experimental channels, called VISA-2 channels. All the channels are made of aluminium tubes, one is sealed to prevent contact of foils with heavy water, and are placed in the regular reactor lattice next to the central experimental channel VK-5. Measuring results, i.e. absolute values of neutron flux and flux distribution are needed for realisation of the VISA-2 project. Measurements of neutron flux are done by activation method. Activation foils are placed in cylindrical aluminium tubes specially prepared for this purpose and placed in VISA-2 channels. Foils are irradiated simultaneously for 5 hours at reactor power of 150 kW. Neutron flux distribution is determined by measuring the relative activity of cobalt foils. [Serbo-Croat] Ovaj izvestaj opisuje merenja neutronskog fluksa u cetiri eksperimentalna kanala VISA-2. Svi VISA-2 kanali nacinjeni su od aluminijuma, jedan je hermeticki zatvoren da folije koje se ozacuju ne dodju ukontakt sa teskom vodom i svi su smesteni neposredno pored centralnog eksperimentalnog kanala VK-5. Rezultati merenja, odnosno apsolutne vrednosti neutronskog fluksa i reposdele fluksa potrebni su za realizaciju projekta VISA-2. Mrerenja neutronskog fluksa izvreseno je aktivacionom tehnikom. Aktivacione folije smestene su u prethodno napravljene aluminijumske cevcice. Folije su ozracivane istovremeno pri snazi od 150 kW pe casova. Raspodela neutronskog fluksa odredjena je merenjem relativne aktivnosti folija od kobalta.

  6. Calculation and measurement of the uranium temperature during irradiation in the experimental channel in the reflector of the RA reactor - Annex 15; Prilog 15 - Proracun i merenje temperature urana pri ozracivanju u eksperimentalnom kanalu reflektora na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-12-15

    Upon demand of the Laboratory for fuel reprocessing, six domestic metal uranium pellets were exposed to neutron flux ( 4 - 5 10{sup 12} n cm{sup -2} sec {sup -1}) in the RA reactor. Irradiation of fuel demanded special analyses for safety reasons. Weight of the fuel pellets was 13 - 20 g, having diameter 20 mm. pellets were placed in leak tight aluminium capsules with helium. The irradiation was dome in the aluminium experimental channel in the graphite reflector. Theoretical study has shown that the expected fuel temperature in the core could be up to 300 deg C at nominal power. For that reason temperature of the capsule with the uranium sample was measured during irradiation by using thermocouples. Results showed the discrepancy between measure and calculated values to be about 30%.

  7. Apatykáři na Starém Městě pražském ve středověku. Příspěvek k možnostem sociotopografické analýzy v areálu pražského souměstí na příkladě osob zabývajících se vykonáváním lékárnického povolání

    Czech Academy of Sciences Publication Activity Database

    Musílek, Martin

    2009-01-01

    Roč. 12, č. 1 (2009), s. 97-137 ISSN 0862-979X Grant - others:AV ČR(CZ) M300090903 Institutional research plan: CEZ:AV0Z90090514 Keywords : Bohemia * Prague * Old Town of Prague * pharmacy * apothecary Subject RIV: AB - History

  8. Activities needed for exploitation of the RA reactor I-IV, Part III, IZ-093-0103-1961; Radovi za potrebe eksploatacije raktora RA - I-IV - III deo, IZ-093-0103-1961

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

    For the purpose of designing the low-temperature loop at the RA reactor, a list of materials that would be irradiated in the reactor was made. This document includes a review of the radiochemistry data for the listed materials and data about thermal stability of the mentioned materials. Calculation of heat generated in listed samples was based on the theoretical and experimental results of radiation characteristics of the RA reactor. Maximum temperature values in the samples without forced cooling are calculated. [Serbo-Croat] Za potrebe projektovanja niskotemperaturne petlje na reaktoru RA nacinjen je pregled materijala za ozracivanje u reaktoru. Ovaj dokument sadrzi pregled radiajaciono hemijskih podataka za navedene materijale i podatke o termickoj stabilnosti pomenutih materijala. Toplota generisana u navedenim uzorcima racunata je uzimajuci u obzir osnovne podatke teorijske i eksperimentalne rezultate odredjivanja karakteristika zracenja u reaktoru. Izracunate su maksimalne temperature u uzorcima bez prinudnog hladjenja.

  9. 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 eksperimentalni podaci za pojedine parametre reaktora uporedjeni su sa izvornim podacima jezgra reaktora RA /12/ i nadjeno je izvanredno slaganje (author)

  10. Experience about performance of experimental facility VISA-2 for materials irradiation by the fast neutron flux at the RA reactor in Vinca; Iskustvo u radu eksperimentalnih uredjaja VISA-2 za ozracivanje materijala u fluksu brzih neutron na reaktoru RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    VISA-2 is an experimental device placed in the core of the RA reactor cooled by heavy water. The objective of constructing this device was irradiation of non-fissile samples of reactor materials in order to test radiation damage. Since the first irradiation program performed in 1962 a number of long-term irradiations were done successfully. This proved the device to be useful and showed new possibilities for RA reactor application. The irradiation programs were performed in cooperation with CEA- Saclay.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

  12. Physical measurements at the RA reactor related to VISA-2, e. Measurements of flux and reactivity during RA reactor operation and exploitation; Fizicka merenja na reaktoru RA u vezi projekta VISA-2, e. Pracenje fluksa i reaktivnosti u toku eksploatacije reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-05-15

    This report includes the following: characteristics of neutron flux in vertical experimental channels of the RA reactor; characteristics of neutron flux in VISA-2 channels; reactivity changes in the reactor during VISA-2 irradiation including calibration of control rods.

  13. 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.

  14. Základy fúzní energetiky II - Základní fyzika fúzních reaktorů

    Czech Academy of Sciences Publication Activity Database

    Entler, Slavomír; Mlynář, Jan; Dostál, V.

    Srpen (2016), č. článku 14538. ISSN 1801-4399 Institutional support: RVO:61389021 Keywords : Nuclear fusion * fusion reactors * plasma Subject RIV: JF - Nuclear Energetics http://energetika.tzb-info.cz/elektroenergetika/14538-zaklady-fuzni-energetiky-ii-zakladni-fyzika-fuznich-reaktoru

  15. 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.

  16. Mikroprogram pre riadenie procesu spájania operandov v architektúre DF KPI

    Directory of Open Access Journals (Sweden)

    Norbert Ádám

    2013-12-01

    Full Text Available V článku uvedená architektúra je založená na výpočtovom modeli „data flow“, v ktorom riadenie výpočtu je založené na spracovaní toku dát. Základným prvkom DF architektúry je koordinačný procesor (CP, ktorý je zodpovedný za riadenie a organizáciu vykonávania inštrukcií. Štruktúrna organizácia CP je navrhnutá ako dynamický multifunkčný systém. Pri vykonávaní operácií môže CP prechádzať rôznymi stavmi, v dôsledku čoho táto jednotka predstavuje dynamický prúdový systém. Prechod a poradie prechodu medzi jednotlivými stavmi CP je podmienený typom spracovaného operátora pri interpretovaní prúdu operandov. Z možných typov operátorov, článok uvádza mikroprogramové riadenie pre jednovstupové operátory.

  17. 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 sa celijama koje sadrze uzorke VISA-2. Ovakvim proracunom moze se proceniti uticaj uzoraka VISA-2 na fluks termanih neutrona u VK-5. Antirektivnost uzoraka VISA-2 izracunata je na bazi difuzione teorije primenom perturbacione metode.

  18. Development of metal fuel and study of construction materials (I-IV), Part V, Vol. II, Project of the device for irradiation of metal uranium in the reactor; 2. Construction of the loop for uranium radiation creep testing; Razvoj metalnog goriva i ispitivanje konstrukcionih materijala (I-VI deo); V deo, Album II, Projekat uredjaja za ozracivanje metalnog urana u reaktoru; 2. Izrada petlje za ispitivanje radijacionog puzanja urana

    Energy Technology Data Exchange (ETDEWEB)

    Mihajlovic, A; Pavlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    This volume includes the design description for construction of the loop for testing uranium radiation creep. It covers the following: construction of the loop head, protection closure; system for pressure regulation and uranium temperature regulation; system for recording samples dilatation and temperature. Testing of components and the loop on the whole is described as well as the safety reports.

  19. 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)

  20. 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)

  1. 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.

  2. Geometrical Image Transforms

    OpenAIRE

    Havelka, Jan

    2008-01-01

    Tato diplomová práce se zabývá akcelerací geometrických transformací obrazu s využitím GPU a architektury NVIDIA (R) CUDA TM. Časově kritické části kódu jsou přesunuty na GPU a vykonány paralelně. Jedním z výsledků je demonstrační aplikace pro porovnání výkonnosti obou architektur: CPU, a GPU v kombinaci s CPU. Pro referenční implementaci jsou použity vysoce optimalizované algoritmy z knihovny OpenCV, od firmy Intel. This master's thesis deals with acceleration of geometrical image transfo...

  3. Pixel Interpolation Methods

    OpenAIRE

    Mintěl, Tomáš

    2009-01-01

    Tato diplomová práce se zabývá akcelerací interpolačních metod s využitím GPU a architektury NVIDIA (R) CUDA TM. Grafický výstup je reprezentován demonstrační aplikací pro transformaci obrazu nebo videa s použitím vybrané interpolace. Časově kritické části kódu jsou přesunuty na GPU a vykonány paralelně. Pro práci s obrazem a videem jsou použity vysoce optimalizované algoritmy z knihovny OpenCV, od firmy Intel. This master's thesis deals with acceleration of pixel interpolation methods usi...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-12-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-12-15

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

  6. Hot cells for testing the UO{sub 2} fuel elements after irradiation. Radiation protection conditions for hot cells design; Vruce celije za ispitivanje gorivnih elemenata UO{sub 2} posle ozracivanja, Uslovi zastite pri projektovanju vrucih celija

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, A; Devic, J; Mihailovic, K [Institut za nuklearne nauke Vinca, Belgrade (Yugoslavia)

    1969-07-01

    This paper includes protection conditions which hot cells should satisfy for the investigation of fuel elements after reactor irradiation. The basic elements of hot cells are given, and the conditions for a special ventilation, dosimetric control and a special treatment of contaminated water are established (author) U radu su obuhvaceni uslovi zastite koje treba da zadovolje vruce celije za ispitivanje gorivnih elemenata posle ozracivanja u reaktoru, dati su osnovni elementi vrucih celija i postavljeni su uslovi za specijalnu ventilaciju, dozimentrijsku kontrolu i specijalni tretman otpadnih voda (author)

  7. 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

  8. 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.

  9. Irradiation tasks within development of fuel elements in Sweden; Rad na ozracivanju u okviru razvoja gorivnih elemenata u Svedskoj

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-11-15

    This report contains description of the hot laboratory RMA for irradiation in the R-2 reactor in Studsvik. Activities of the AB Atomenegiyu concerning irradiation and testing of fuel rods and fuel elements are described, as well as methods for testing of irradiated samples in hot cells. Concerning the importance of the problem, determination of burnup level and neutron flux were examined particularly. Dat je opis vruce metalurske laboratorije RMA i sistema za ozracivanje u reaktoru R-2 u Studsviku. Prikazana je aktivnost AB Atomenergy u okviru razvoja gorivnih elemenata na ozracivanju i ispitivanju ozracenog goriva, gorivnih sipki i sklopova gorivnih elemenata. Prikazane su metode ispitivanja ozracenih uzoraka u vrucim celijama. S obzirom na vaznost problema, posebno je razradjeno pitanje odredjivanja stepena izgaranja i fluksa neutrona (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-12-15

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

  12. 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)

  13. 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.

  14. Technical realisation of the VISA-II Project, Phase II, Chapter X, Vol. VI; Tehnicka realizacija projekta VISA-II, II faza, Glava X, Album VI

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-01-15

    The second phase of the 'Project VISA-2 described in this chapter of Vol. VI includes the project specifications and technical drawings of the 'measuring system of VISA-2 for testing the VISA-2 channels outside and in the reactor'. In addition to the task objective, description of the measuring system, action plan, description of the work done it contains the definition of the task 'Leak testing' and instructions for the instrumentation personnel on duty. [Serbo-Croat] Druga faza zadatka {sup T}ehnicka realizacija projekta VISA-2' opisana u ovom poglavlju Albuma VI, sadrzi tehnicki opis i crteze 'Mernog sistema VISA-2 i ispitivanje kanala VISA-2 van reaktora i u reaktoru'. Pored definicije zadatka, opisa mernog sistema VISA-2, razrade zadatka, tekstualnog dela projekta i opisa izvedenih radova, ovo poglavlje obuhvata definiciju i razradu podzadatka 'Ispitivanje hermeticnosti' i dodatak sa instrukcijama za dezurne instrumentatore u vezi eksperimenta VISA-2.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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

  20. New Rules for Acquisition of Agricultural Land – – Case of Slovakia / Nové Pravidlá Pre Nadobúdanie Vlastníctva K Poľnohospodárskej Pôde – – Prípad Slovenska

    Directory of Open Access Journals (Sweden)

    Lazíková Jarmila

    2015-06-01

    Full Text Available Príspevok analyzuje vývoj právnej úpravy devízového zákona vo vzťahu k nadobúdaniu pôdy cudzincami vrátane nového zákona č. 140/2014 Z.z. o nadobúdaní vlastníctva poľnohospodárskeho pozemku a o zmene a doplnení niektorých zákonov, ktorý vstúpil do platnosti 1. Júna 2014. Tento zákon neobmedzuje len nadobúdanie pôdy cudzincami, ale aj občanmi Slovenska. Na základe zákona, vlastník poľnohospodárskej pôdy na Slovensku je oprávnený bez ďalších obmedzení previesť pozemok do vlastníctva (a osobe, ktorá vykonáva poľnohospodársku výrobu ako podnikanie najmenej tri roky predo dňom uzavretia zmluvy o prevode vlastníctva poľnohospodárskeho pozemku v obci, v ktorej sa poľnohospodársky pozemok nachádza, (b spoluvlastníkovi poľnohospodárskeho pozemku, (c príbuznej osobe, v prípade, že vlastníkom je fyzická osoba.

  1. 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.

  2. 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

    i citavog primarnog kola reaktora kobaltom; 1970. godine - zbog slanja teske vode u Francusku na izotopsku regeneraciju; 1979/80. i 1983. godine - zbog talozenja aluminijum oksihidrata na kosuljicama gorivnih elemenata u aktivnoj zoni reaktora i 1985/86. godine - zbog rekonstrukcije sistema ventilacije i izgradnje sistema za hladjenje jezgra reaktora u nuzdi. RA je tip teskovodnog istrazivackog reaktora sa sudom. Kod njega teska voda sluzi i kao moderator neutrona i kao primarni hladilac. Od pocetka rada, na reaktoru je korisceno 2% obogaceno uransko metalno gorivo. Od 1976. godine, na reaktoru je pocelo da se delimicno koristi 80% obogaceno oksidno uransko gorivo, da bi se od 1981. godine, na reaktoru koristilo isklucivo ovo visokoobogaceno gorivo. Reaktor RA je tako projektovan da mu snaga u normalnom radnom rezimu bude 6,5 MW, a u forsiranom 10 MW. Kao izvor neutrona, reaktor je namenjen za istrazivanja u oblasti reaktorske i neutronske fizike, fizike cvrstog stanja, radijacione hemije, biologije, a narocito za proizvodnju readioaktivnih izotopa. Reaktor RA su izgradila jugoslovenska gradjevinska i montazna preduzeca, na osnovu sovjetskog projekta. U SSSR su fabrikovane glavne komponente njegovih sistema i uredjaja.

  3. 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

    je jedanput mesecno. U ovom izvestajnom periodu na reaktoru RA bilo je zaposleno prosecno 42 radnika, sto je dovoljan broj u uslovima remontnih i investicionih radova. Nedostatak finansijskih sredstava za odrzavanje reaktora RA je neresen problem i u ovom periodu. Ovaj izvestaj podeljen je u dve celine: (1) pogon i odrzavanje reaktora i (2) zastita od zracenja na reaktoru RA.

  4. 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

  5. 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)

  6. External irradiation of the personnel operating the reactor RA at Vinca in the period 1963-1966; Spoljasnje ozracivanje osoblja koje opsluzuje reaktor RA u Vinci u periodu 1963-1966

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M M; Minincic, Z [Institut za nuklearne nauke Vinca, Belgrade (Yugoslavia)

    1967-07-01

    The objective of this paper was the analysis of external radiation exposure of the personnel employed at the RA reactor in Vinca during past four years. During 1963 reactor was not operated because of the general repair and maintenance, and it was operated during 1964, 1965 and 1966. The internal irradiation and the estimation of the beta doses on the skin were not analysed in this paper, they should be treated by separate analyses. The evaluation of external irradiation covered only gamma radiation since yhe neutron doses were negligible. The analysis was based on the the irradiation dose data obtained by film and personal dosemeters. Predmet ovog rada je analiza spoljasnjeg ozracivanja osoblja koje je radilo na reaktoru RA u Vinci u poslednje cetiri godine, u toku kojih je reaktor bio u opstem remontu 1963, odnosno u normalnom radu 1964, 1965 i 1966. U ovom radu nismo se upustali u analizu unutrasnjeg ozracivanja, kao ni procenu doza beta zracenja na kozi, sto treba da bude predmet posebnih analiza. Pri proceni spoljasnjeg ozracivanja operisano je samo sa dozama gama zracenja, jer je ozracivanje neutronima zanemarljivo. Celokupna analiza izvrsena je na osnovu podataka o dozama ozracivanja do kojih se doslo ocitavanjem film o penkalo dozimetara.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-05-15

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

  8. 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.

  9. 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.

  10. 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.

  11. External irradiation of the personnel operating the reactor RA at Vinca in the period 1963-1966; Spoljasnje ozracivanje osoblja koje opsluzuje reaktor RA u Vinci u periodu od 1963. do 1966. godine

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-06-15

    The paper first gives a survey of the characteristic operations performed on the Vinca reactor RA in which most of the personnel become irradiated. Following is a schematic diagram of the irradiations in the period 1963-1966 in which the reactor was in continual operation. The surveys are given for each month and each year separately, while the irradiated personnel are grouped in several characteristic irradiation dose ranges. In this analysis special emphasis is given to a survey of irradiation of the personnel classified according to their profession, i.e. their post. This kind of analysis is indispensable in planning work, proper disposition of the personnel and undertaking special protective measures for reducing the irradiations (author) [Serbo-Croat] U radu je najpre dat pregled mesta na reaktoru RA, sa topografijom zracenja, na kojima radno osoblje pretezno biva ozracivano. Zatim su dati tabelarno i graficki pregledi ozracivanja za protekli period u kome je reaktor neprekidno radio, tj. od 1963. do 1966. god. Pregledi su dati po mesecima za svaku godinu i to tako sto su ozracivana lica razvrstavana u nekoliko karakteristicnih intervala doza ozracivanja. Posebno mesto u ovoj analizi zauzima pregled ozracivanja osoblja razvrstanog po strukama, odnosno radnim mestima. Ovakva analiza je nuzna za planiranje poslova, pravilan raspored radnog osoblja kao i preduzimanje posebnih zastitnih mera u cilju smanjivanja ozracivanja (author)

  12. 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.

  13. 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.

  14. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

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

  16. 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.

  17. 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.

  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. 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)

  20. Technical realisation of the VISA-II project, phase I, part IV, IZ-165-o268-1962; Tehnicka realizacija projekta VISA-II, I faza (I-V), IV deo, IZ-165-o268-1962

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-12-15

    Project VISA-II is described in IX chapters as follows: introduction, definition of experiments and possibilities of performance; VISA-II channel, new experimental space in the RA reactor; hydraulic tests in the VISA-II channel; measurement of fast neutron and gamma flux in VISA-II channels; measurement of water flow through different VISA-2 irradiation capsules; fabrication of VISA-II capsules; corrosion and heavy water purity problems; safety problems of experiment VISA-2; experimental operation of VISA-II. This chapter VI includes documentation for each type of capsule, review about each experiment within the VISA-II project, the objective and purpose of the experiment as well as experimental device. [Serbo-Croat] Projekat VISA-2 opisan je u sledecih IX poglavlja: uvod, definicija eksperimenta VISA-2 i mogucnost njegovog izvodjenja; kanal VISA-2 novi eksperimentalni prostor u reaktoru RA; hidraulicna ispitivanja na tehnoloskom kanalu VISA-2; Realizacija merenja fluksa brzih neutrona i gama zracenja u kanalima VISA-2; merenje protoka vode kroz razne tipove kapsula VISA-2; Kapsule VISA-2 i njihova realizacija; problemi korozije i cistoce teske vode u projektu VISA-2; problemi sigurnosti eksperimenta VISA-2; probni pogon eksperimenta VISA-2. Ova VI glava elaborata sadrzi dokumentaciju za svaku vrstu kapsula, preglednu sliku o svakom eksperimentu u okviru projekta VISA-2, o njegovom cilju i nameni kao i o eksperimentalnom uredjaju.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

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

  2. 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

    pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije je u toku, ali njegova realizacija u 1994. godini 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 ugovoru trebalo je da celokupna nova instrumentacija za reaktor RA bude isporucena Institutu u Vinci do kraja 1990. godine, ali je do septembra 1991. godine isporuceno svega 56% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju izrecena od strane ove organizacije Ujedinjenih nacija. U 1991. godini na reaktoru RA je demontirana postojeca instrumentacija u maksimalno mogucem obimu, kako bi se zadrzala neka osnovna merenja neophodna i u uslovima kada reaktor nije u pogonu. U 1994. godini nastavljen je rad na razradi i dopuni sovjetskog projekta. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Veoma obiman remont sekundarnog kola hladjenja reaktora privodi se kraju i bice okoncan u prvoj polovini 1995. a u skladu postojecim zakonskim propisima i sa preporukama MAAE. Kontrola goriva od strane inspektora MAAE obavljana je jedanput mesecno. Na reaktoru RA u 1994. godini radilo je prosecno 47 radnika, sto je dovoljan broj u uslovima remontnih i investicionih radova.

  3. 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

    ugovoru trebalo je da celokupna nova instrumentacija za reaktor RA bude isporucena Institutu u Vinci do kraja 1990. godine, ali je 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 izrecena od strane ove organizacije Ujedinjenih nacija. Demontirana je postojeca instrumentacija u maksimalno mogucem obimu, kako bi se zadrzala neka osnovna merenja neophodna i u uslovima kada reaktor nije u pogonu. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Kontrola goriva od strane inspektora MAAE obavljana je jedanput mesecno. U ovom izvestajnom periodu na reaktoru RA bilo je zaposleno prosecno 43 radnika, sto je dovoljan broj u uslovima remontnih i investicionih radova. Nedostatak finansijskih sredstava za odrzavanje reaktora RA je neresen problem i u ovom periodu. Ovaj izvestaj podeljen je u dve celine: pogon i odrzavanje reaktora i zastita od zracenja na reaktoru RA.

  4. 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

    firmom Atomenergoexport. Prema tom ugovoru trebalo je da celokupna nova instrumentacija za reaktor RA bude isporucena Institutu u Vinci do kraja 1990. godine, ali je do septembra 1991. godine isporuceno svega 56% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju izrecena od strane ove organizacije Ujedinjenih nacija. Demontirana je postojeca instrumentacija u maksimalno mogucem obimu, kako bi se zadrzala neka osnovna merenja neophodna i u uslovima kada reaktor nije u pogonu. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Kontrola goriva od strane inspektora MAAE obavljana je jedanput mesecno. U ovom izvestajnom periodu na reaktoru RA bilo je zaposleno prosecno 47 radnika, sto je dovoljan broj u uslovima remontnih i investicionih radova. Nedostatak finansijskih sredstava za odrzavanje reaktora RA je neresen problem i u ovom periodu. Ovaj izvestaj podeljen je u dve celine: pogon i odrzavanje reaktora i zastita od zracenja na reaktoru RA.

  5. 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

    zahvat, koji se odnosi na zamenu celokupne instrumentacije je u toku, ali njegova realizacija u 1991. godini 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 ugovoru trebalo je da celokupna nova instrumentacija za reaktor RA bude isporucena Institutu u Vinci do kraja 1990. godine, ali je do septembra 1991. godine isporuceno svega 56% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju izrecena od strane ove organizacije Ujedinjenih nacija. U 1991. godini na reaktoru RA je demontirana postojeca instrumentacija u maksimalno mogucem obimu, kako bi se zadrzala neka osnovna merenja neophodna i u uslovima kada reaktor nije u pogonu. Pri kraju je izrada odredjenih konstrukcionih elemenata za novu instrumentaciju, koju je prihvatio da realizuje Institut u Vinci, kako bi se ubrzala realizacija ovog projekta. Ako sva predvijena oprema ne bude isporucena do kraja marta 1992. godine, nece moci da se otpocne sa probnim radom reaktora u prvoj polovini 1993. godine, kako je planirano. Na realizaciji projekta u 1991. godini ucestvovalo je efektivno 53 radnika, sto je dovoljan broj u uslovima remontnih i investicionih radova. 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.

  6. Preparation of the capsule for the experiment with enriched fuel, task E-14-16-00-29; Priprema kapsula za eksperiment sa obogacenim gorivom, zad. E-14-16-00-29

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-12-15

    Preparation of the experiment with highly enriched fuel was based on the experience gained in constructing the capsule for natural uranium fuel. The possibility of using capsules with enriched UO{sub 2} in the RA reactor was analyzed. Special attention was devoted to the analysis of heat removal from the fuel rods. Capsule for irradiation of enriched UO{sub 2} was designed. The most important change appeared in sealing zircaloy-2 with stainless steel part. This must be done by diffusion welding. Since there is no device for diffusion welding in our country the elements will be sent to Saclay, France. All the parts made of domestic material were fabricated in the Institute. Purchase of elements that must be imported is delayed due to procedures for obtaining foreign currency. The fabrication of the capsule can be completed within 25 days upon obtaining the mentioned material from abroad. This report contains the safety report for the experiment with the enriched fuel. Na osnovu dosadasnjeg rada i iskustva na izgradnji kapsula za neobogaceno gorivo izvrsena je priprema za eksperimenat sa obogacenim gorivom. Analizirana je mogucnost koriscenja kapsula sa obogadenim UO{sub 2} u reaktoru RA. Narocito je posvecena paznja analizi odvodjenja generisane toplote iz sipki gorivnih elemenata. Projektovana je kapsula za ozracivanje obogacenog UO{sub 2}. Najznacajnija izmena je kod spajanja dela od cirkaloja-2 sa delom od nerdjajuceg celika. To spajanje morace se izvrsiti na masini za difuziono zavarivanje. Kako takvu masinu nemamo u zemlji elemente cemo dati da se zavare u Saclay-u. Svi delovi za koje nije bio potreban uvozni materijal izradjeni su u nasem Institutu. Kapsula nije montirana jer materijal iz uvoza koji se ugradjuje u kapsulu nije jos stigao u zemlju. Nabavka uvoznlh elemenata nije izvrsena na vreme zbog zakasnjenja kod odobravanja deviznih sredstava. Potpuna montaza kapsule moze se obaviti 25 dana po dobijanju pomenutog materijala. U radu je dat i izvestaj o

  7. 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.

  8. 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

  9. Measurement of nuclear reactor noise at low power levels; Merenje nuklearnog reaktorskog suma na malim snagama

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-11-15

    Spatial and time dependence relation of neutrons from fission and other reactions in the reactor core result in non Poisson fluctuations of neutron density. Analytical formula developed for auto-correlation function includes physical parameters which characterize time behaviour of neutrons in the reactor system. Since auto-correlation function can be easily measured, it is a useful tool for experimental determination of these parameters. Noise from the ionization chamber was measured and analyzed by a digital computer. measurements were analyzed completely in the time domain (auto-correlation functions). This enabled separating the noise caused by neutron detection from the noise from neutron density fluctuation in the reactor. All the results can be analyzed by spatial independent reactor theory. Physical analysis of reactor noise was limited to determination of {beta}/l ratio from auto-correlation measurements at 0.5 W power level (RB reactor in Vinca). Three different reactor core lattices were analyzed (lattice pitch 8 cm, 11.3 cm and 14 cm). It was shown that parameter {beta}/l could be determined from auto-correlation measurements of neutron density with high precision (few percents) Prostorna i vremenska povezanost neutrona koji nastaju u fisiji i drugim procesima koji se desavaju u reaktoru dovodi do ne Poisson-ovih fluktuacija neutronske gustine. Analiticka formula, razvijena za autokorelacionu funkciju ovih fluktuacija, sadrzi fizicke parametre koji karakterisu vremensko ponasanje neutrona u reaktorskom sistemu. Kako autokorelaciona funkcija moze lako da se meri, ona je korisno sredstvo za eksperimentalno odredjivanje ovih parametara. Sum iz jonizacione komore digitalno je meren i analiziran u digitalnom racunaru. Merenja su kompletno analizirana u vremenskom domenu (autokorelacione funkeije). To je olaksalo razdvajanje suma izazvanog procesom neutronske detekcije od suma koji potice od fluktuacija neutronske gustine u reaktorskom sistemu. Svi rezultati

  10. 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

  11. 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

    ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina, iz kojih se moze videti da je ozracivanje u proteklom periodu 1986. godine bilo na nivou prethodnih godina izuzimajuci delimicno 1985. godinu. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. U zavrsnom delu izvestaja, analizirani su akcidenti koji su se desili na reaktoru tokom 1986. Zakljuceno je da nije bilo akcidenata koji bi imali za posledicu znacajniju kontaminaciju radnih povrsina i opreme, kao ni kontaminaciju i ozracivanje osoblja.

  12. 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

    ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. U zavrsnom delu izvestaja, analizirani su akcidenti koji su se desili na reaktoru tokom 1985. Zakljuceno je da nije bilo akcidenata koji bi imali za posledicu znacajniju kontaminaciju radnih povrsina i opreme, kao ni kontaminaciju i ozracivanje osoblja.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-10-15

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

  14. 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

  15. 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

  16. 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

  17. 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

  18. Hodnocení variability dynamických parametrů chůze u osob s jednostrannou trans-tibiální amputací The variability assessment of the dynamic gait parameters of persons with unilateral trans-tibial amputation

    Directory of Open Access Journals (Sweden)

    Milan Elfmark

    2006-02-01

    Full Text Available Při analýze pohybové činnosti člověka musíme vždy řešit otázky, které se vztahují k validitě naměřených hodnot. Realizace každého pohybu, tedy i chůze, se vyznačuje určitou mírou variability. Přitom variabilitu v určitém rozsahu nelze považovat jako něco negativního, co může být způsobeno problémy v nervovém nebo kosterně-svalovém systému. "Přirozená" variabilita (varia bilita ve "fyziologickém" rozsahu je součástí zdravých biologických systémů. Reedukace chůze u osob s trans-tibiální amputací se projevuje ve změně variability kinematických a dynamických charakteristik. Pro možnost kvantifikace těchto změn a pro určení vlivu různých typů protetických chodidel (klasické – SACH, dynamické – SUREFLEX jsme provedli dynamickou analýzu chůze u 11 mužů (věk 46,1 ± 12,0 roku, hmotnost 82,5 ± 13,9 kg s jednostrannou trans-tibiální amputací. Interindividuální variabilita v rámci dané skupiny je větší v porovnání s intraindividuální variabilitou. Hodnoty koeficientu reliability jsou pro měřené parametry (čas, síla, impuls síly v antero-posteriorním a ve vertikálním směru větší než 0,976. Jejich velikost souvisí s individuálními vlastnostmi sledovaných osob. Pro oba typy protetického chodidla, podobně jako pro zdravou končetinu, jsou tendence pro stabilitu dynamických parametrů podobné. Stabilita měřených parametrů v medio-laterálním směru se významně snižuje uvnitř sledované skupiny i pro jednotlivé osoby. Velikost variability při různé rychlosti chůze souvisí se zdravotním stavem a se stupněm pohybové aktivity daného probanda. Pro osoby, které vykonávají běžné denní aktivity v omezeném rozsahu, je variabilita dynamických parametrů chůze nižší při použití klasického chodidla. Human gait is a genetically fixed motion model. The use of prosthesis changes the structure of the gait, the distribution of

  19. 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

    Start of utilization of the new 80% enriched dispersion nuclear fuel is underway in the RA reactor core. Both economic and technical analyses were in favor of introducing the new fuel elements gradually into the RA reactor core. Thus overall theoretical and experimental analyses as well as other preparations are directed to transition regime based on gradual introducing of new fuel into the core, i.e. reactor core with two types of fuel. The objective of these analyses and preparation is establishment of conditions for safe reactor operation during transition period. The analyses and preparations are almost completed. The experimental data about fuel burnup during a time period of operation at nominal power i.e. daily decrease of excess reactivity is missing. This data is needed for planning the refueling (quantity of fresh fuel and frequency of refueling) during the transient period. This data can be obtained only by normal operation of the reactor during a period of time significantly longer than the period of attaining equilibrium poisoning, as time between two D{sub 2}O condensate overflows into the RA reactor core. Thus a ten day experimental campaign was planned to be done in December 1976. This report presents the most important results of safety analyses and preparation which show that, during this experimental period, the reactor operation is absolutely safe taking into account the most important parameters influencing reactor safety, as reactivity, thermal and temperature limits for fuel and the reactor, etc. Data to be obtained during this experimental campaign are significant because they would enable definition of future supply of fresh fuel during the transition period. [Serbo-Croat] Predstoji pocetak koriscenja novog 80% obogacenog uranskog disperzionog goriva u reaktoru RA. Ekonomske i tehnicke analize dale su prednost postupku postepenog uvodjenja novog goriva u reaktor RA. Prema tome, obimne teorijske i eksperimentalne analize i druge pripreme

  20. 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

    tako su zadovoljeni a u medjuvremenu je objavljen novi pravilnik po kome se pomenuti uslovi vise ne zahtevaju za reaktore snage manje od 10MW, a snaga reaktora RA je 6,5 MW. Medjutim ranije izdato naredjenje o prekidu rada reaktora nije ukinuto. Reaktor nije poceo sa radom i usled najvece rekonstrukcije, zamene celokupne instrumentacije koja je planirana da traje do kraja 1991. godine. Program obuke radnika koji rade u pogonu i odrzavanje reaktora sacinjen je 1985. godine. Rekonstrukcija, modifikacija i izgradnja novih sistema na reaktoru RA zahtevali su i izradu novih dokumenta za dalji siguran i bezbedan rad reaktora. Nova verzija Sigurnosnog izvestaja reaktora RA zavrsena je 1986. u skladu sa preporukama MAAE i 'Pravilnikom o izradi i sadrzaju izvestaja o sigurnosti i druge dokumentacije potrebne za utvrdjivanje sigurnosti nuklearnih objekata' (objavljenom novembra 1988. godine). U novembru 1989. zavrsena je izrada dokumenta koji sadrzi nove propise i uputstva za rad i eksploataciju reaktora RA. Reaktorska petlja projektovana 1986. izgradjena je i ispitana 1990. Sve reaktorske komponente odrzavale su redovno posebno formirane sluzbe, za instrumentaciju, masinsku i elektroopremu. Nedovoljna sredstva za pogon i odrzavanje opreme reaktora RA predstavljaju veliki problem za uspesno i efikasno obavljanje poslova.

  1. Muscle activation in healthy subjects during single step up [Aktivace svalů u zdravých osob při nákroku na schod

    Directory of Open Access Journals (Sweden)

    Jaroslav Opavský

    2010-03-01

    muscle → right gluteus maximus muscle. Greater differences in the sequence of the muscle involvement were found on the side of the supporting leg. CONCLUSIONS: In conclusion, the findings have indicated that there exists variability in patterns of muscle activation during the step up task.[VÝCHODISKA: Nákrok na schod je součástí běžných denních motorických aktivit. Při jeho provádění musí být tělo schopno udržovat rovnováhu a stabilní vzpřímenou posturu za současného průběhu volního pohybu. K tomuto účelu vytváří centrální nervová soustava různé motorické programy, specifické pro daný úkol a obsahující předem programované sekvence zapojování svalů k zajištění provedení vlastního pohybu a k udržení postury během vykonávaného pohybu. CÍLE: Cílem práce bylo určení časové posloupnosti zapojení vybraných svalů trupu a dolních končetin při nákroku na schod. Dalším cílem bylo zjištění nejběžnějšího vzoru zapojování svalů v této modelové pohybové aktivitě u zdravých osob. METODIKA: U této práce byla snímána bilaterálně elektromyografická aktivita m. gluteus maximus, m. biceps femoris a m. erector spinae (v jeho lumbální části. Spolu s elektromyografickým signálem snímaným povrchovými elektrodami byl zaznamenáván i vizuální záznam provedení nákroku na schod. Soubor tvořilo 16 zdravých mladých probandů, všichni praváci (5 mužů, průměrný věk 23,6 let a 11 žen, průměrný věk 23,2 let, u kterých byly anamnesticky vyloučeny úrazy dolních končetin a páteře. Na povel nakročili probandi spontánní rychlostí na schod (výška schodu = 20 cm pravou dolní končetinou. Pohybový úkol končil došlápnutím levou dolní končetinou na schod. Elektromyografické záznamy jednotlivých svalů byly hodnoceny z hlediska časového nástupu aktivace svalů ve vztahu k začátku pohybu pravé dolní končetiny, který byl určen podle videozáznamu. Časy n

  2. The quality of kindergarten care as an important element of the subjective theories [Kvalita předškolní péče jako důležitý prvek subjektivních teorií

    Directory of Open Access Journals (Sweden)

    Maja Meško

    2012-03-01

    žitím statistického programu SPSS ve Windows. Každý statisticky významný závěr byl přijat na úrovni rizika 5%. VÝSLEDKY: Analýza výsledků ukázala, že názory předškolních učitelů a asistentů na způsob, jakým děti tráví volný čas, nebyly statisticky rozdílné. Nicméně, byly zde rozdíly týkající se hodnocení množství a kvality sportovního vybavení a rozdíly v jejich postojích k motorickým/sportovním aktivitám, a to ve prospěch předškolních učitelů, kteří navíc vykonávají motorické/sportovní aktivity častěji než asistenti. Rovněž jsme zjistili, že čím více předškolní učitelé realizují motorické/sportovní aktivity během týdne, tím častěji také realizují motorické/sportovní aktivity v mateřské škole. ZÁVĚRY: Výsledky našeho výzkumu nás vedou k tomu, abychom realizovali širší výběr seminářů v rámci profesní přípravy učitelů také pro asistenty. Zároveň také k tomu, abychom přemýšleli o poskytování rekreačních aktivit pro zaměstnance mateřských škol, které by přispěly k celkovému bio-psycho-sociálnímu postavení jednotlivce a změnily jejich životní styl ze sedavého na aktivní.

  3. Presentation of the results for deuterium retention and thermal release in a new type of low activation ferritic-martensitic steel EUROFER / Результаты исследования по удержанию дейтерия и термической десорбции в условиях низкой активации ферритно-мартенситной стали EUROFER / Rezultati zadržavanja i termalne desorpcije deuterijuma u EUROFER-u, novoj vrsti feritno-martenzitnog čelika niske aktivacije

    Directory of Open Access Journals (Sweden)

    Sanja Lj. Korica

    2016-04-01

    žđu, hromu i EOROFER-u, leguri koja se razmatra kao najnoviji materijal za buduće fuzione reaktore. Studija je pokazala sledeće rezultate: zadržavanje deuterijuma u hromu je mnogo veće nego u gvožđu (usled formiranja hidrida hroma, zadržavanje deuterijuma u EUROFER-u je za faktor 2 veće nego u gvožđu, primećena je specifična struktura u koncentracionom profilu gvožđa i EUROFER-a na dubini ~ 4 μm, veliki stepen difuznosti i zadržavanja deuterijuma govore o potencijalnoj upotrebi Au kao difuzione barijere u fuzionom reaktoru.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-03-15

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

  5. Handling and Separation of Short-Lived Radioisotopes from Research Reactors; Manipulation et Separation des Radioisotopes a Courte Periode Produits dans des Reacteurs de Recherche; ПОЛУЧЕНИЕ И ОТДЕЛЕНИЕ КОРОТКОЖИВУЩИХ ИЗОТОПОВ В ИССЛЕДОВАТЕЛЬСКИХ РЕАКТОРАХ; Manipulacion y Separacion de Radioisotopos de Periodo Corto Obtenidos en Reactores de Investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Meinke, W. W. [University of Michigan, Ann Arbor, MI (United States)

    1963-03-15

    iz-za udalennosti ot snabzhavshego reaktora chasto ogranichivalos' temi, kotorye imeet period poluraspada bol'she odnogo dnja. Jeto tormozilo issledovanija v oblasti proizvodstva i primenenija radioizotopov voobshhe i v to zhe vremja meshalo potrebitele tochno ocenit' vozmozhnosti mnogih korotkozhivushhih izotopov. V svjazi s nalichiem vo vsem mire issledovatel'skih reaktorov jeta zavisimost' ot mesta proizvodstva izotopov mozhet predstavljat' soboj izvestnuju trudnost', no v to zhe vremja ona daet vozmozhnost' provodit' rjad novyh jeksperimentov s korotkozhivushhimi izotopami. Dlja jetogo trebuetsja vplotnuju podojti k voprosam proizvodstva mechenyh atomov. Pochti v techenie pjati let programma raboty ka issledovatel'skom reaktore Michiganskogo universiteta vkljuchala obrabotku, pererabotku i izmerenie korotkozhivushhih izotopov. Obychno pol'zovalis' izotopami, prodolzhitel'nost' poluraspada kotoryh ravnjalas' chasam i dazhe minutam. Hotja v dannom sluchae glavnye usilija byli napravleny na issledovanija v oblasti aktivacionnogo analiza, ispol'zovavsheesja oborudovanie i metodika mogut byt' primeneny i dlja drugih issledovanij. Dlja poluchenija korotkozhivushhih izotopov ne objazatel'no imet' sovershennoe oborudovanie, bol'shie zapasy izotopov ili podderzhivat' trehsmennuju rabotu reaktora. Pri uverennom obrashhenii s prostymi manipuljatorami mozhno poluchit' luchshie rezul'taty, chem distancionnym upravleniem. Osnovoj sistemy, opisyvaemoj v doklade, javljaetsja prisposoblenie v vide pnevmaticheskoj truby, kotoraja dostavljaet obrazcy v vytjazhnoj kolpak laboratorii, primykajushhej k reaktoru, v techenie treh sekund posle obluchenija. Rastvorenie i bystroe otdelenie radiohimicheskim sposobom mozhet proizvodit'sja bez dal'nejshego peremeshhenija obrazca. Metody otdelenija, legko prisposablivaemye dlja kratkovremennoj shkaly (neskol'ko minut), vkljuchajut ne tol'ko selektivnuju jekstrakciju, anionnyj obmen i osazhdenie, no i takie novye metodiki, kak izotopnyj obmen i

  6. 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

    'noj laboratorii, gde sooruzhaetsya kriticheskaya sborka na bystrykh nejtronakh - ZPR-VI na ee stantsii po izucheniyu fiziki reaktorov na bystrykh nejtronakh v Lemonte, shtat Illinojs. ZPR-VI yavlyaetsya ustrojstvom s dvumya dvizhushchimisya polovinami aktivnoj zony, kotoroe analogichno reaktoru ZPR-III. On imeet ob'em priblizitel'no v dva s polovinoj raza prevyshayushchij ob'em bolee rannego reaktora, i budet ispol'zovat'sya dlya issledovanij fiziki krupnykh sistem na sil'no razbavlennom toplive, metallicheskom i metallokeramichesko m toplive, bez zamedleniya ili s chastichnym zamedleniem, imeyushchim ob'emy aktivnoj zony priblizitel'no do 1500 litrov. V doklade budet dano podrobnoe opisanie ZPR-VI i budut obsuzhdeny kriterii, kotorye ispol'zovalis' pri proektirovanii ego razlichnykh komponentov s tochki zreniya reaktornoj fiziki. Krome togo, v doklad budut vklyucheny takie voprosy, kak upravlenie i ehkspluatatsiya, potentsial'naya opasnost' vo vremya ehkspluatatsii, ehksperimental'ny e metody i stoimost' stroitel'stva. (author)