Published August 1985 | Version v1
Journal article Metadata-only

Analysis of the maximum credible accident in a fast reactor core

Creators

Description

Principal stages and after-effects of an accident connected with blanking of the flow section of the BN-600 type reactor fuel assembly (FA) are considered. Quantitative characteristics of the processes of sodium boiling, gas release from the fuel elements, fuel and FA can melting, interaction of molten fuel with sodium are obtained. The time of the accident spread to the neighrbouring FAs in case of instantaneous blanking of the damaged FA is proved to be 15 s. It determines the requirement to be met by the control and safety systems as to their fast response

Additional details

Additional titles

Original title (Russian)
Анализ максимальной проектной аварии в активной зоне быстрого реактора

Publishing Information

Journal Title
At. Ehnerg.
Journal Volume
59
Journal Issue
2
Series
At. Ehnerg.
Journal Page Range
112-116
ISSN
0004-7163
CODEN
AENGA

INIS

Country of Publication
Russian Federation
Country of Input or Organization
USSR
INIS RN
17036838
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BELOYARSK-3 REACTOR; BOILING; COOLANTS; FISSION PRODUCT RELEASE; FUEL ASSEMBLIES; FUEL CANS; FUEL-COOLANT INTERACTIONS; GASES; MAXIMUM CREDIBLE ACCIDENT; MELTING; NUCLEAR FUELS; RUPTURES; SHROUDS; SODIUM; TIME DEPENDENCE; VOID COEFFICIENT
Descriptors DEC
ACCIDENTS; ALKALI METALS; BREEDER REACTORS; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; FLUIDS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS

Optional Information

Notes
For English translation see the journal Soviet Journal of Atomic Energy (USA).