Published 1993 | Version v1
Report Open

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.

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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).

Optional Information

Contract/Grant/Project number
Contract AC02-76CH00016
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
CONF-930116--36.