Published October 1991 | Version v1
Journal article Metadata-only

Numerical analysis of the initial phase of the Chernobyl accident

Creators

  • 1. Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (Russian Federation). Inst. Atomnoj Ehnergii
  • 2. AN Ukrainskoj SSR, Kiev (Ukraine). Inst. Yadernykh Issledovanij

Description

The results of numerical analysis of conditions of rod dropping from the state of the Chernobyl-4 reactor just before the accident, are considered. Three-dimensional program of neutron kinetics and by-channel program of hydrodynamics were used for investigation. Sufficient sensitivity of energy release maximum to spatial distribution of neutron flux in initial state is revealed. Factors, which contributed to accident realization, are enumerated. The scenario of accident development is formulated

Additional details

Additional titles

Original title (Russian)
Расчетный анализ начальной стадии аварии на Чернобыльской AEhS

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
71
Journal Issue
4
Journal Page Range
p. 275-287.
ISSN
0004-7163
CODEN
AENGAB

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
24059676
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
CHERNOBYLSK-4 REACTOR; COMPUTERIZED SIMULATION; D CODES; FINITE DIFFERENCE METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; POWER DISTRIBUTION; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; SPATIAL DISTRIBUTION; THEORETICAL DATA; TIME DEPENDENCE; VOID FRACTION
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; DATA; DISTRIBUTION; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; ITERATIVE METHODS; LWGR TYPE REACTORS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS