Published April 1991 | Version v1
Report

WWER plant probabilistic safety assessment

  • 1. All-Union Research Inst. for Nuclear Power Plant Operations (VNIIAES), Moscow (USSR)

Description

This paper addresses the ways of probabilistic safety assessment for WWER-1000 reactors in operation. Probabilistic analysis is supposed to be used to optimize operational documentation, to assess weaknesses and enhance safety and efficiency of the operating plants. Probabilistic safety assessment (PSA) is a necessary part of safety justification for NPPs both operating and under design. To practically implement the task much effort is needed to process information, prepare computers codes, to do calculations and adopt the results. Operational experience shows that WWER plants can be improved by improving stability, reducing the number of shutdowns, labour consumption as well as improving operational documentation and taking account of all hypothetical transients. The best possible way to achieve this goal is to use PSA. In this paper PSA performance programme adopted in VNIIAES is described. (author). 6 figs, 1 tab

Part of:
Use of probabilistic safety assessment to evaluate nuclear power plant technical specifications

Additional details

Publishing Information

Imprint Title
Use of probabilistic safety assessment to evaluate nuclear power plant technical specifications
Imprint Pagination
293 p.
Journal Page Range
p. 139-151.
Report number
IAEA-TECDOC--599

Conference

Title
Technical committee meeting on the use of probabilistic safety assessment to evaluate nuclear power plant technical specifications.
Dates
18-22 Jun 1990.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22081113
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DOCUMENTATION; MODIFICATIONS; PROBABILISTIC ESTIMATION; REACTOR OPERATION; REACTOR SAFETY; SAFETY ANALYSIS; WWER-5 REACTOR
Descriptors DEC
ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information