Published 2022 | Version v1
Book

Determination of the spent fuel decay heat with the VERA core simulator

  • 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)
Part of:
Proceedings of the international conference on physics of reactors - Physor 2022

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.