Published June 2005 | Version v1
Report Metadata-only

PSA-2 study and its application during the development and assessment of SAMG guidelines

Creators

Description

The relations between Level 2 probabilistic safety assessment (PSA-2) and severe accident management guidelines (SAMG) are outlined. In addition to relations of general nature, specific examples are given of PSA-2 for Czech nuclear power plants and generic SAMG of Westinghouse, based on which SAMG for Czech NPPs were developed. An example of SAMG validation by PSA-methods is given for the Dukovany NPP. (author)

Availability note (English)

Available (also in the electronic format as a PDF reproduction) from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.cz, ric@nri.cz

Additional details

Additional titles

Original title (Czech)
Studie PSA-2 a jeji aplikace pri tvorbe a hodnoceni navodu SAMG
Augmented title (English)
[Severe Accident Management Guidelines]

Publishing Information

Imprint Pagination
[42 p.]
Report number
UJV--12241-T

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
38085507
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
DUKOVANY-1 REACTOR; HYPOTHETICAL ACCIDENTS; MITIGATION; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RECOMMENDATIONS; RISK ASSESSMENT; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Notes
Developed within the State Office for Nuclear Safety project 'Investigation into and development of provisions to lower the risks and mitigate consequences of severe accidents at NPPs in the Czech Republic based on advanced experimental and analytical methods'. 1 tab., 2 figs., 28 refs.