The use of probabilistic risk assessment in the safety assessment of Hanford nuclear facilities
Description
The Probabilistic Risk Assessment of the Hanford Site started about 3 year ago. The first facility studied was the N Reactor. This paper reports on a limited-scope Probabilistic Risk Assessment that was completed in 1987 that showed the N Reactor met U.S. Nuclear Regulatory Commission Probabilistic Risk Assessment goals and its risk to the public was comparable to the commercial industry. An N reactor Level 3 Probabilistic Risk Assessment is under way and is scheduled for completion September 1989. The Level 1 phase is complete and results indicate a core damage frequency of 6.4 E-05/yr. A Fast Flux Test Facility Probabilistic Risk Assessment was started January 1989 and is due to be completed January 1992. Other major Probabilistic Risk Assessment activities are anticipated for the nonreactor facilities presently operating and planned at the Hanford Site
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-89448-142-8
- Imprint Title
- Probability, reliability, and safety assessment PSA '89
- Imprint Pagination
- 1300 p.
- Journal Page Range
- p. 1077-1083.
Conference
- Title
- international topical meeting on probability, reliability and safety assessment.
- Acronym
- PSA '89
- Dates
- 2-7 Apr 1989.
- Place
- Pittsburgh, PA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059735
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; FFTF REACTOR; FREQUENCY RESPONSE TESTING; HANFORD ENGINEERING DEVELOPMEN; N-REACTOR; PLANNING; PROBABILISTIC ESTIMATION; PUBLIC HEALTH; RADIATION PROTECTION; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; RISK ASSESSMENT; US NRC
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; LWGR TYPE REACTORS; MEDICINE; NATIONAL ORGANIZATIONS; PLUTONIUM PRODUCTION REACTORS; POWER REACTORS; PREVENTIVE MEDICINE; PRODUCTION REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; TESTING; US DOE; US ORGANIZATIONS; WATER COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-890405--.