Published June 2004 | Version v1
Journal article Metadata-only

Estimations of irradiated graphite radiation characteristics for RBMK NPP decommission

Creators

  • 1. RNTs Kurchatovskij Inst., Moscow (Russian Federation)
  • 2. Leningradskaya AEhS, Sosnovyj Bor (Russian Federation)

Description

Procedure for the calculation of radiation characteristics of RBMK irradiated graphite laying is described. Spatial distribution of neutron flux density in graphite volume was evaluated by the MCNP program, isotope ratio and radiation characteristics of irradiated graphite - by the CHAIN program on the basis of fluxes calculated by MCNP program. Results of the calculation of radiation characteristics of graphite of the Leningrad-1, Leningrad-1 and Chernobylsk-1 reactors are presented, contribution of fuel overflow accident in laying is estimated

Abstract (Russian)

Описана методика расчета радиационных характеристик облученного графита кладки РБМК. Пространственное распределние плотности потока нейтронов в объеме графита определяли по программе MCNP, изотопный состав и радиационные характеристики облученного графита - по программе CHAIN на основании потоков, рассчитанных по MCNP. Приведены результаты расчета радиационных характеристик графита реакторов 2-го и 3-го блоков Ленинградской АЭС и 1-го блока Чернобыльской АЭС, оценен вклад аварии с выходом топливной массы в кладку

Additional details

Additional titles

Original title (Russian)
Расчетные оценки радиационных характеристик облученного графита после окончательного останова АЭС с RBMK

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
96
Journal Issue
6
Journal Page Range
p. 451-457
ISSN
0004-7163
CODEN
AENGAB

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
37037148
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
C CODES; CHERNOBYLSK-1 REACTOR; GRAPHITE; ISOTOPE RATIO; LENINGRAD-2 REACTOR; LENINGRAD-3 REACTOR; M CODES; NEUTRON FLUX; RADIOACTIVITY; REACTOR ACCIDENTS; REACTOR DECOMMISSIONING; REACTOR SAFETY; SPATIAL DISTRIBUTION
Descriptors DEC
ACCIDENTS; CARBON; COMPUTER CODES; DECOMMISSIONING; DIMENSIONLESS NUMBERS; DISTRIBUTION; ELEMENTS; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; MINERALS; NONMETALS; POWER REACTORS; RADIATION FLUX; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS

Optional Information

Notes
5 refs., 4 figs., 1 tab.