Monte Carlo calculations for recriticality during the reflood phase of a severe accident in a BWR
Creators
- 1. Los Alamos National Lab., NM (United States)
- 2. Electric Power Research Inst., Palo Alto, CA (United States)
Description
Monte Carlo calculations were performed to assess the possibility of recriticality during the core relocation phase of a severe accident in boiling water reactors (BWRs). The MCNP Monte Carlo code was chosen both because of its inherent accuracy for such calculations and because many continuous-energy isotopic cross-section libraries based on ENDF/B-V were already available for it. These results suggest that a BWR core may be able to remain subcritical during reflood even when a large fraction of the control rod has been lost. In fact, it appears as if the core might remain subcritical even if 60 or 70% of the boron content of the affected control rods were lost. However, additional calculations at those conditions would be required to determine a realistic estimate of the amount of boron that could be lost without producing criticality
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 254
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036652
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BWR TYPE REACTORS; CONTROL ELEMENTS; CORIUM; CRITICALITY; CROSS SECTIONS; FISSION PRODUCTS; HEAT TRANSFER; HYDRAULICS; MELTING; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR KINETICS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; ISOTOPES; KINETICS; MATERIALS; PHASE TRANSFORMATIONS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910603--.