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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.9
- 수록면
- 2,803 - 2,815 (13page)
- DOI
- https://doi.org/10.1016/j.net.2021.03.010
이용수
초록· 키워드
오류제보하기
This paper addresses the uncertainty quantification and sensitivity analysis of a depleted light-water fuelassembly of the Turkey Point-3 benchmark. The uncertainty of the fuel assembly decay heat and isotopicdensities is quantified with respect to three different groups of diverse parameters: nuclear data, assembly design, and reactor core operation. The uncertainty propagation is conducted using a two-stepanalysis code system comprising the lattice code STREAM, nodal code RAST-K, and spent nuclear fuelmodule SNF through the random sampling of microscopic cross-sections, fuel rod sizes, number densities, reactor core total power, and temperature distributions. Overall, the statistical analysis of thecalculated samples demonstrates that the decay heat uncertainty decreases with the cooling time. Thenuclear data and assembly design parameters are proven to be the largest contributors to the decay heatuncertainty, whereas the reactor core power and inlet coolant temperature have a minor effect. Themajority of the decay heat uncertainties are delivered by a small number of isotopes such as 241Am, 137Ba, 244Cm, 238Pu, and 90Y.
ⓒ 2021 Korean Nucl
목차
등록된 정보가 없습니다.
참고문헌 (11)
참고문헌 신청
장재림 / 2021 / Validation of spent nuclear fuel decay heat calculation by a two-step method / Nuclear Engineering and Technology 53(1):44~60
장재림 / 2021 / Verification and validation of isotope inventory prediction for back-end cycle management using twostep method / Nuclear Engineering and Technology 53(7):2104~2125
M. B. Chadwick / 2011 / ENDF/B-VII.1 nuclear data for science and technology:cross sections, covariances, fission product yields and decay data / Nucl. Data Sheets 112(12):2887~2996
최지원 / 2019 / Verification and Validation of STREAM/RAST-K for PWR Analysis / Nuclear Engineering and Technology 51(2):356~368
R. Arcilla / 2008 / Processing neutron cross section covariances using NJOY-99and PUFF-IV / Nucl. Data Sheets 109(12):2910~2914
장재림 / 2021 / Verification and validation of isotope inventory prediction for back-end cycle management using twostep method / Nuclear Engineering and Technology 53(7):2104~2125
M. B. Chadwick / 2011 / ENDF/B-VII.1 nuclear data for science and technology:cross sections, covariances, fission product yields and decay data / Nucl. Data Sheets 112(12):2887~2996
최지원 / 2019 / Verification and Validation of STREAM/RAST-K for PWR Analysis / Nuclear Engineering and Technology 51(2):356~368
R. Arcilla / 2008 / Processing neutron cross section covariances using NJOY-99and PUFF-IV / Nucl. Data Sheets 109(12):2910~2914
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