Published February 1997
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Health and safety impact of steam generator tube degradation
Description
In this paper the author addresses the problems inherent in evaluating the safety of steam generators with respect to tube rupture as part of a probabilistic safety analysis (PSA) of a reactor plant. He reviews the history of PSA as applied to reactors, and then looks at tube rupture histories as a start toward establishing event frequencies. He considers tube ruptures from the aspect of being an initiating event to being a conditional event to some other event, and then the question of performance of the steam generator in the face of a severe accident in the reactor
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants
- Imprint Pagination
- 621 p.
- Journal Page Range
- p. 559-566.
- Report number
- NUREG/CP--0154
Conference
- Title
- CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants.
- Dates
- 30 Oct - 2 Nov 1995.
- Place
- Oak Brook, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28068431
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEFECTS; PROBABILISTIC ESTIMATION; REACTORS; RISK ASSESSMENT; RUPTURES; SAFETY ANALYSIS; STEAM GENERATORS; TUBES
- Descriptors DEC
- BOILERS; FAILURES; VAPOR GENERATORS
Optional Information
- Secondary number(s)
- ANL--96/14; NEA/CNRA/R--(96)1; CONF-9510423--.