TY - GEN
T1 - Determination of the Spent Fuel Decay Heat with the VERA Core Simulator
AU - Kromar, Marjan
AU - Godfrey, Andrew T.
N1 - Publisher Copyright:
© 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.
PY - 2022
Y1 - 2022
N2 - 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 Krško 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.
AB - 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 Krško 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.
KW - CASL
KW - core simulator
KW - decay heat
KW - spent nuclear fuel
KW - VERA
UR - https://www.scopus.com/pages/publications/85184961718
U2 - 10.13182/PHYSOR22-37862
DO - 10.13182/PHYSOR22-37862
M3 - Conference contribution
AN - SCOPUS:85184961718
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
SP - 166
EP - 175
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
PB - American Nuclear Society
T2 - 2022 International Conference on Physics of Reactors, PHYSOR 2022
Y2 - 15 May 2022 through 20 May 2022
ER -