Evaluation of light-water-moderated, mixed-oxide, hexagonal pitch lattices
Description
The use of previously measured mixed-oxide (MOX) fuel systems as benchmarks can be valuable tool in computational analysis and quality assurance efforts. The Fissile Materials Disposition Program (FMDP) has identified these experiments as potential benchmarks, or standards, for VVER's employing MOX fuel. Standards for the analysis of these benchmark experiments were based on those used in the recent compilation International Handbook of Evaluated Criticality Safety Benchmark Experiments begun in 1992 by the U.S. Department of Energy. The Los Alamos National Laboratory's archives were explored for log-book records of these experiments without success. These experiments were the first to use MOX fuel in light water. Three approach-to-critical experiments were performed using fuel rods at various pitches and different plutonium-oxide concentrations. A parallel program verified the prediction of critical condition as similar materials and geometries were actually brought to critical. The computational analyses presented in this paper support the measurement results and their designation as benchmark-quality work
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 77
- Journal Page Range
- p. 363-364.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1997 American Nuclear Society (ANS) winter meeting.
- Dates
- 16-20 Nov 1997.
- Place
- Albuquerque, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29021099
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; CRITICALITY; FUEL RODS; HEXAGONAL CONFIGURATION; MIXED OXIDE FUELS; NEUTRON FLUX; PWR TYPE REACTORS; QUALITY ASSURANCE; REACTOR LATTICES
- Descriptors DEC
- CONFIGURATION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-971125--.