Probabilistic risk analysis of HCDA scenarios in a pool-type breeder reactor
Description
One potential design for the future generation of nuclear reactors is that of the breeder reactor. As with present-day reactors there is the necessity for demonstrating that such a reactor will be operable with very small risk to the public. As a result, a probabilistic risk analysis (PRA) will be a valuable tool in the design of future nuclear plants. This paper presents a risk analysis performed to evaluate hypothetical core disruptive accidents (HCDAs) in a large, pool-type LMFBR, and how it was used to evaluate the reduction in risk brought about by the addition of various safety-related design options. It was shown that the base design met the NRC risk guidelines with some margin, and that a design option featuring emergency cooling of the reactor vessel greatly reduced the risk
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE85000092.Files
16054764.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- CONF-850206--6
Conference
- Title
- International ANS/ENS topical meeting on probabilistic safety methods and applications.
- Dates
- 24-28 Feb 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16054764
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LMFBR TYPE REACTORS; PROBABILITY; REACTOR CORE DISRUPTION; RISK ANALYSIS; SAFETY ENGINEERING; SPECIFICATIONS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS