A probabilistic analysis of rapid boron dilution scenarios
Description
A probabilistic and deterministic analysis of a rapid boron dilution scenario related to reactor restart was performed. The event is initiated by a loss of off-site power during the startup dilution process. The automatic restart of the charging pump in such cases may lead to the accumulation of a diluted slug of water in the lower plenum. The restart of the reactor coolant pumps may send the diluted slug through the core, adding sufficient reactivity to overcome the shutdown margin and cause a power excursion. The concern is that the power excursion is sufficient in certain circumstances to cause fuel damage. The estimated core damage frequency based on the scoping analysis is 1.0--3.0E-05/yr for the plants analyzed. These are relatively significant values when compared to desirable goals. The analysis contained assumptions related to plant specific design characteristics which may lead to non-conservative estimates. The most important conservative assumptions were that mixing of the injected diluted water is insignificant and that fuel damage occurs when the slug passes through the core
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE93006388; NTIS; INIS; US Govt. Printing Office Dep.Files
24038815.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- BNL-NUREG--48227
Conference
- Title
- Probabilistic safety assessment international topical meeting (PSA 93).
- Dates
- 27-29 Jan 1993.
- Place
- Clearwater Beach, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038815
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON; DILUTION; EXCURSIONS; PROBABILISTIC ESTIMATION; PUMPS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR START-UP; WATER
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ELEMENTS; ENRICHED URANIUM REACTORS; EQUIPMENT; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SEMIMETALS; START-UP; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC02-76CH00016
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-930116--36.