Published March 2003
| Version v1
Journal article
Variants of modernization of BIR and BIGR reactors for the purpose of enlargement of their inner cavities
- 1. RFYaTs - VNIIEhF, Sarov (Russian Federation)
Description
Results of calculated neutron characteristics of BIR and BIGR fast pulse reactors, namely, cylindric systems with the core zone involving 90 %- and 36 % uranium enriched alloy with 10 % by mass of molybdenum or composite uranium-graphite material are presented. Neutron characteristics of the reactors were calculated by means of the S-95 code by the Monte Carlo method with the aim of possible increasing inner cavities in the reactors without pronounced degradation of time parameters of impulses. Disk reactor core systems with the axial cavity by the diameter to 30 cm and iron reflector limited by the width are the most acceptable
Abstract (Russian)
Приведены результаты расчетов нейтронных характеристик быстрых импульсных реакторов типа БИР и БИГР, а именно цилиндрических систем с активной зоной из сплава урана 90 %- или 36 %-ного обогащения с 10 % по массе молибдена или композитного уран-графитового материала. Нейтронные харктеристики реакторов рассчитывали с помощью программы С-95 метода Монте-Карло с целью возможного увеличения внутренних полостей в реакторах без заметного ухудшения временных параметров импульсов. Наиболее приемлемыми признаны системы с дисковой активной зоной, имеющей осевую полость диаметром до 30 см и ограниченный по толщине железный отражательAdditional details
Additional titles
- Original title (Russian)
- Varianty modernizatsii BIR i BIGR v tselyakh uvelicheniya ikh vnutrennikh polostej
Publishing Information
- Journal Title
- Atomnaya Ehnergiya
- Journal Volume
- 94
- Journal Issue
- 3
- Journal Page Range
- p. 175-184
- ISSN
- 0004-7163
- CODEN
- AENGAB
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 35081200
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BIGR REACTOR; BIR REACTOR; CAVITIES; COMPOSITE MATERIALS; CYLINDRICAL CONFIGURATION; EXPERIMENTAL CHANNELS; GRAPHITE; MOLYBDENUM ALLOYS; MONTE CARLO METHOD; NEUTRON FLUX; PROMPT NEUTRONS; REACTOR CORES; S CODES; URANIUM 235; URANIUM BASE ALLOYS
- Descriptors DEC
- ACTINIDE ALLOYS; ACTINIDE NUCLEI; ALLOYS; ALPHA DECAY RADIOISOTOPES; BARYONS; CALCULATION METHODS; CARBON; COMPUTER CODES; CONFIGURATION; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EVEN-ODD NUCLEI; FAST REACTORS; FERMIONS; FISSION NEUTRONS; GRAPHITE MODERATED REACTORS; HADRONS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINERALS; MINUTES LIVING RADIOISOTOPES; NEUTRONS; NONMETALS; NUCLEI; NUCLEONS; PULSED REACTORS; RADIATION FLUX; RADIOISOTOPES; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; TRANSITION ELEMENT ALLOYS; URANIUM ALLOYS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 6 refs., 5 figs., 5 tabs.