Systematic approach to containment performance criteria
Description
The objective of this study is to demonstrate how to specify containment performance criteria in a systematic way given top level safety goals. The multiobjective optimization approach proposed by Cho, et al. was adopted as a method for deriving a finite manageable set of self-consistent relations between the top level safety goals and specific sets of measures of containment performance. The current trial safety goals proposed by the NRC goes from a design objective figure of 10-4 for annual frequency of core melt to guideline numbers for early fatalities and for delayed fatalities. An alternative is to specify containment system performance in some quantitative fashion. If this can be done, and if the specified performance can be demonstrated with some reasonable level of confidence, it will help to provide greater consistency between top level safety goals (health risk indices) and lower level design objectives (plant performance indices, i.e., core melt frequency and containment performance criteria)
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI86007123.Files
18019602.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- BNL-NUREG--37691
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 15-20 Jun 1986.
- Place
- Reno, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18019602
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT BUILDINGS; CONTAINMENT SYSTEMS; HEALTH HAZARDS; PERFORMANCE; PWR TYPE REACTORS; REACTOR SAFETY; RELIABILITY; SPECIFICATIONS; US NRC
- Descriptors DEC
- BUILDINGS; CONTAINMENT; ENRICHED URANIUM REACTORS; HAZARDS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-860610--16.