Published March 1994 | Version v1
Report

The PSA programme in VUPEX Bratislava

Creators

  • 1. VUPEX, J.S. Co., Bratislava (Czech Republic)

Description

The areas in which VUPEX is active reflect problems arising in the nuclear power plant operation. Main field of activities are systems analyses which include reliability analyses of safety systems, probabilistic safety assessment and fire protection for WWER 440s. The system reliability analyses are concentrated on the front-line and support systems of V213 and V230 type reactors. Examples are the high pressure safety system and reactor building spray system of V230 type reactors and numerous single system studies sponsored by utility for design, review and reconstruction purposes. The fault tree method by TREE MASTER code has been used for analyses. VUPEX performs research into Probabilistic Safety Assessment within the Level 1 PSA study of the unit 1 of Dukovany Nuclear Power Plant. The work was started in 1989 and the Level 1 study will be finished in 1993. The systems analysed in VUPEX are those V213 type front-line systems identified in event trees. Also analysed are the support systems whose action is required by the front-line systems during the course of an accident. The RISK SPECTRUM-PSA code is used for analyses. (author)

Part of:
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors

Additional details

Publishing Information

Imprint Title
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors
Imprint Pagination
264 p.
Journal Page Range
p. 71-72.
ISSN
1011-4289
Report number
IAEA-TECDOC--737

Conference

Title
Technical committee meeting on advances in reliability analysis and probabilistic safety assessment for nuclear power reactors.
Dates
7-11 Sep 1992.
Place
Budapest (Hungary).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
25037043
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FAULT TREE ANALYSIS; FIRE PREVENTION; PROBABILISTIC ESTIMATION; R CODES; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SUPPORTS; T CODES; WWER-3 REACTOR
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; MECHANICAL STRUCTURES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information