A PWR Thorium Pin Cell Burnup Benchmark - 275
Creators
- 1. Department of Nuclear Engineering, Massachusetts Institute of Technology,Cambridge, MA 02139 (United States)
- 2. Idaho National Engineering and Environmental Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415-3850 (United States)
- 3. Department of Fluid Dynamics and Power Engineering, School of Mechanical Engineering, Czech Technical University, Technicka 4, 166 07 Prague 6 (Czech Republic)
Description
As part of work to evaluate the potential benefits of using thorium in LWR fuel, a thorium fueled benchmark comparison was made in this study between state-of-the-art codes, MOCUP (MCNP4B + ORIGEN2), and CASMO-4 for burnup calculations. The MOCUP runs were done individually at MIT and INEEL, using the same model but with some differences in techniques and cross section libraries. Eigenvalue and isotope concentrations were compared on a PWR pin-cell model up to high burnup. The eigenvalue comparison as a function of burnup is good: the maximum difference is within 2% and the average absolute difference less than 1%. The isotope concentration comparisons are better than a set of MOX fuel benchmarks and comparable to a set of uranium fuel benchmarks reported in the literature. The actinide and fission product data sources used in the MOCUP burnup calculations for a typical thorium fuel are documented. Reasons for code vs code differences are analyzed and discussed. (author)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 14 p.
Conference
- Title
- ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium
- Acronym
- Physor 2000
- Dates
- 7-12 May 2000
- Place
- Pittsburgh, PA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54119275
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNUP; EIGENVALUES; FISSION PRODUCTS; MIXED OXIDE FUELS; NUCLEAR DATA COLLECTIONS; PWR TYPE REACTORS; THORIUM; URANIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; ISOTOPES; MATERIALS; METALS; NUCLEAR FUELS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)