Published February 1997 | Version v1
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Health and safety impact of steam generator tube degradation

Creators

  • 1. PLG, Inc., Newport Beach, CA (United States)

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

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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

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