Published 1983
| Version v1
Report
Restricted
Evaluation of the sensitivity of reactor risks to uncertainties
Description
The increase in the use of Probabilistic Risk Assessment (PRA) in the evaluation of nuclear reactor safety has prompted a need for evaluation of the sensitivity of PRA results to specific uncertainties. This paper discusses results from the evaluation of the sensitivity of reactor risks to uncertainty in the in-vessel steam explosion probability, containment failure pressure, source term release magnitudes, site population density, and interdiction dose criterion. These uncertainties are addressed individually; potential synergistic effects are not considered. Examination of the uncertainties should enhance the use of PRA as applied to the evaluation of nuclear reactor safety
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE83016883.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- SAND--83-0855C
Conference
- Title
- International meeting on light-water reactor severe accident evaluation.
- Dates
- 28 Aug - 1 Sep 1983.
- Place
- Cambridge, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15002018
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ECONOMICS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ANALYSIS
- Descriptors DEC
- ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-830816--32.