Published 2005 | Version v1
Journal article Metadata-only

Model of neutron flow density distribution in fuel containing materials of 'Ukryttya' object room 305/2

Creators

  • 1. Institut problem bezopasnosti AEhS NAN Ukrainy, Chernobyl' (Ukraine)
  • 2. Institut yadernykh issledovanij, Kyiv (Ukraine)

Description

The version of three-dimensional model of location, structure, and fraction of total mass of chemical elements in FCM accumulations of 'Ukryttya' object Room 305/2 is proposed. Calculation results of neutron flow density (NFD) distribution obtained using the Program MCNP-4C are represented. Calculation results are compared with data of direct measurements of NFD

Additional details

Additional titles

Original title (Russian)
Модель распределения плотности потока нейтронов в объеме топливосодержащих материалов помещения 305/2 объекта «Укрытие»

Publishing Information

Journal Title
Problems of Chernobyl
Journal Volume
2
Journal Page Range
p. 55-60
ISSN
1727-3390

INIS

Country of Publication
Ukraine
Country of Input or Organization
Ukraine
INIS RN
37029699
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Descriptors DEI
CHEMICAL COMPOSITION; CHERNOBYLSK-4 REACTOR; COMPUTERIZED SIMULATION; CORIUM; LAVA; M CODES; MATHEMATICAL MODELS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; SHELTERS; SPATIAL DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; IGNEOUS ROCKS; LWGR TYPE REACTORS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; ROCKS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS