SRS's production reactor severe-accident issues
- 1. Westinghouse Savannah River Co., Aiken, SC (United States)
Description
Severe accident behavior in Al-U metal-fueled production reactors is sufficiently different from commercial oxide-fueled reactors that an ongoing research and development (R and D) effort is needed to resolve issues specific to metal-fueled systems. The severe-accident program at the Savannah River Site (SRS) is based on light water reactor (LWR) technology when appropriate. A direct application of severe-accident phenomena technology developed from oxide-fueled LWRs to metal-fueled heavy water reactors (HWRs) can lead to large errors or substantial uncertainties. The value of applying severe-accident LWR concepts to Al-U-fueled HWRs is in defining the relevant issues, defining differences, and in determining areas of overlap. The paper provides a summary of the major issues and phenomena affecting severe-accident response in a metal-fueled HWR and an LWR. SRS has an aggressive ongoing research and development effort that is identifying and finding solutions to a wide range of issues for beyond-design-basis severe accidents
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Journal Page Range
- p. 377-378.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics.
- Dates
- 10-15 Nov 1991.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24016016
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY NUCLEAR FUELS; ALUMINIUM; BWR TYPE REACTORS; CRITICALITY; FUEL ELEMENT FAILURE; HEAT TRANSFER; HEAVY WATER; HYDRAULICS; MELTDOWN; MELTING; MITIGATION; POWER DENSITY; PWR TYPE REACTORS; REACTIVITY; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR KINETICS; REACTOR VESSELS; RESEARCH PROGRAMS; SAVANNAH RIVER PLANT; SPECIAL PRODUCTION REACTORS; URANIUM; US DOE
- Descriptors DEC
- ACCIDENTS; ACTINIDES; CONTAINERS; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUELS; HYDROGEN COMPOUNDS; KINETICS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FUELS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; POWER REACTORS; PRODUCTION REACTORS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; US AEC; US ERDA; US ORGANIZATIONS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911107--.