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