Published July 1992 | Version v1
Journal article Metadata-only

Probabilistic modelling of the WWER-440 nuclear power plant accident sequences

Creators

Description

The results of the analysis, made within the frames of the IAEA program of coordinated research dealing with probabilistic modelling of accident consequences, are presented. The accident with intermediate loss of coolant in the primary circuit and deenergizing of the Paksh NPP unit 2 with WWER-440 reactor is studied. Description of accident probabilistic models with failure of some safety systems is presented and approach to failure analysis and personnel actions is specified. Conditional probabilities for realization of the model under consideration are obtained

Additional details

Additional titles

Original title (Russian)
Вероятностное моделирование аварийных последовательностей для АЭС с ВВЭР-440

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
73
Journal Issue
1
Journal Page Range
p. 54-60.
ISSN
0004-7163
CODEN
AENGAB

Conference

Title
Nuclear technology tomorrow.
Original Conference Title
3. Ezhegodnaya nauchno-tekhnicheskaya konferentsiya yadernogo obshchestva 'Yadernye tekhnologii v zavtrashnem mire'
Dates
14-18 Sep 1992.
Place
Sankt-Peterburg (Russian Federation).

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
25052677
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ECCS; EFFICIENCY; FAILURES; FAULT TREE ANALYSIS; HUMAN FACTORS; IAEA; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR OPERATORS; RESEARCH PROGRAMS; RISK ASSESSMENT; SAFETY ANALYSIS; SIMULATION; WWER TYPE REACTORS
Descriptors DEC
ACCIDENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; INTERNATIONAL ORGANIZATIONS; PERSONNEL; POWER REACTORS; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS