Determination of the spent fuel decay heat with the VERA core simulator
Creators
- 1. Jozef Stefan Institute, Jamova 39, SI-1000, Ljubljana (Slovenia)
- 2. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
Description
VERA core simulator capabilities to predict spent fuel decay heat have been explored. Comparison with the Serpent2 and NEWT/TRITON sequence from the SCALE package, performed on the NPP Krsko fuel test cases, has enabled the validation of the VERA calculation sequence. Since the VERA is a 3-D core simulator, the focus in the rest of the paper was on the investigation of the 3-D effects and nonlinearity of the soluble boron concentration averaging process, which are difficult to assess with majority of available calculation tools. A difference in the decay heat prediction between the 3-D and 2-D model approaches has been analyzed. In addition, the impact of the Inconel grids on the decay heat was determined. Averaging of the soluble boron concentration over the fuel irradiation period has been found to be a viable approach, since it results in slight decay heat overprediction, which is considered conservative for the most applications. Finally, demonstration on the Watts Bar Unit 1 cycle 1 depletion has shown formidable VERA capabilities to accurately predict spent fuel decay heat. (authors)
Availability note (English)
Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)Additional details
Publishing Information
- Publisher
- ANS - American Nuclear Society
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-787-3
- Imprint Title
- Proceedings of the international conference on physics of reactors - Physor 2022
- Imprint Pagination
- 3701 p.
- Journal Page Range
- p. 192-201
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR 2022
- Dates
- 15-20 May 2022
- Place
- Pittsburg (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53096941
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; BENCHMARKS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; S CODES; SPENT FUELS; TIME DEPENDENCE; V CODES
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; SIMULATION
Optional Information
- Notes
- 8 refs.