In-core thermal-hydraulic and fission product calculations for severe fuel damage analyses
Creators
- 1. Fauske ampersand Associates, Inc., Burr Ridge, IL (USA)
Description
Best-estimate calculations of realistic fission product source terms are presented for the Severe Fuel Damage (SFD) tests conducted in the Power Burst Facility (PBF), utilizing the Advanced Reactor Severe Accident Program (ARSAP) bulk mass transfer correlation. Computer codes were written to perform the thermal-hydraulic and fission product calculations for the SFD tests. Fewer and slower releases are predicted with the ARSAP mass transfer correlation, in good agreement with the test results. The ARSAP mass transfer model correlates the inverse fuel temperature with the product of release rate and grain size considering the fuel/cladding interaction. The empirical coefficients were developed from Oak Ridge National Laboratory (ORNL) high-burnup fuel data in the 770 to 2,275 K temperature range. The ORNL test data indicate that the fuel/cladding interaction takes effect above 2,000 K
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 60
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 744-746
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085620
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNUP; BWR TYPE REACTORS; COMPUTER CODES; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL INTEGRITY; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; HYDRAULICS; ORNL; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SOURCE TERMS; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-891103--.