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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.1
- 수록면
- 44 - 60 (17page)
- DOI
- https://doi.org/10.1016/j.net.2020.06.028
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초록· 키워드
오류제보하기
In this paper, we validate the decay heat calculation capability via a two-step method to analyze spentnuclear fuel (SNF) discharged from pressurized water reactors (PWRs). The calculation method isimplemented with a lattice code STREAM and a nodal diffusion code RAST-K. One of the features of thismethod is the direct consideration of three-dimensional (3D) core simulation conditions with theadvantage of a short simulation time. Other features include the prediction of the isotope inventory byLagrange non-linear interpolation and the use of power history correction factors. The validation isperformed with 58 decay heat measurements of 48 fuel assemblies (FAs) discharged from five PWRsoperated in Sweden and the United States. These realistic benchmarks cover the discharge burnup rangeup to 51 GWd/MTU, 23.2 years of cooling time, and spanning an initial uranium enrichment range of2.100e4.005 wt percent. The SNF analysis capability of STREAM is also employed in the code-to-codecomparison. Compared to the measurements, the validation results of the FA calculation with RAST-Kare within ±4%, and the pin-wise results are within ±4.3%. This paper successfully demonstrates thatthe developed decay heat calculation method can perform SNF back-end cycle analyses.
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참고문헌 (24)
참고문헌 신청
Status of spent fuel storage for the first quarter of 2019
J, Jang / 2020 / Verification and Validation of Back-End Cycle Source Term Calculation of the Nodal Code RAST-K / PHYSOR 2020: Transition to a Scalable Nuclear Future
S. Choi / 2017 / Resonance treatment using pin-based pointwise energy slowing-down method / J. Comput. Phys 330:134~155
S. B Ebiwonjumi / 2018 / Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory / Ann. Nucl. Energy 120:431~449
S. B Ebiwonjumi / 2019 / Verification and validation of radiation source term capabilities in STREAM / Ann. Nucl. Energy 124:80~87
J, Jang / 2020 / Verification and Validation of Back-End Cycle Source Term Calculation of the Nodal Code RAST-K / PHYSOR 2020: Transition to a Scalable Nuclear Future
S. Choi / 2017 / Resonance treatment using pin-based pointwise energy slowing-down method / J. Comput. Phys 330:134~155
S. B Ebiwonjumi / 2018 / Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory / Ann. Nucl. Energy 120:431~449
S. B Ebiwonjumi / 2019 / Verification and validation of radiation source term capabilities in STREAM / Ann. Nucl. Energy 124:80~87
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