Published 1996
| Version v1
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Core damage frequency (reactor design) perspectives based on IPE results
Description
This paper provides perspectives gained from reviewing 75 Individual Plant Examination (IPE) submittals covering 108 nuclear power plant units. Variability both within and among reactor types is examined to provide perspectives regarding plant-specific design and operational features, and C, modeling assumptions that play a significant role in the estimates of core damage frequencies in the IPEs. Human actions found to be important in boiling water reactors (BWRs) and in pressurized water reactors (PWRs) are presented and the events most frequently found important are discussed
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE97003198; NTIS; US Govt. Printing Office Dep.Files
28057272.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- SAND--97-0339C
Conference
- Title
- 24. water reactor safety information meeting.
- Dates
- 21-23 Oct 1996.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28057272
- 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; HUMAN FACTORS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-94AL85000
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-9610202--5.