Published 1988 | Version v1
Book

An assessment of the low seismic risk of the inherently safe sodium advanced fast reactor (SAFR)

  • 1. Rockwell International Corp., Canoga Park, CA (USA). Rocketdyne Div.

Description

A recent probabilistic risk assessment (PRA) of the sodium advanced fast reactor (SAFR) demonstrated the inherently low risk of advanced liquid-metal, pool-type fast reactors with inherent safety systems. As a result, it was recognized that external events, especially seismic events, may not only be a major contributor to risk (as shown in several LWR PRAs) but also may completely dominate the risk. Accordingly, a seismic risk assessment has been completed for SAFR, which resulted in a core damage frequency of 2 x 10-7/year and a large release frequency of 4 x 10-9/year. This paper reports that public health risk in terms of early fatality risk and latent fatality risk were also several orders of magnitude below the NRC safety goals and below recent LWR risks reported in NUREB/CR1150

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
89448-1460-0
Imprint Title
Proceedings of the international topical meeting on safety of next generation power reactors
Imprint Pagination
933 p.
Journal Page Range
p. 57-63.

Conference

Title
American Nuclear Society topical meeting on the safety of next generation power reactors.
Dates
1-5 May 1988.
Place
Seattle, WA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22023558
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
REACTOR SAFETY; RISK ASSESSMENT; SAFETY ENGINEERING; SEISMIC EFFECTS; SODIUM COOLED REACTORS
Descriptors DEC
LIQUID METAL COOLED REACTORS; REACTORS; SAFETY

Optional Information

Secondary number(s)
CONF-880506--.