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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.1
- 수록면
- 19 - 29 (11page)
- DOI
- https://doi.org/10.1016/j.net.2020.06.016
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초록· 키워드
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This paper presents the validation of the MCS code for critical safety analysis with burnup credit for thespent fuel casks. The validation process in this work considers five critical benchmark problem sets,which consist of total 80 critical experiments having MOX fuels from the International Criticality SafetyBenchmark Evaluation Project (ICSBEP). The similarity analysis with the use of sensitivity and uncertaintytool TSUNAMI in SCALE was used to determine the applicable benchmark experiments correspondingto each spent fuel cask model and then the Upper Safety Limits (USLs) except for the isotopicvalidation were evaluated following the guidance from NUREG/CR-6698. The validation process in thiswork was also performed with the MCNP6 for comparison with the results using MCS calculations. Theresults of this work showed the consistence between MCS and MCNP6 for the MOX fueled criticalitybenchmarks, thus proving the reliability of the MCS calculations
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참고문헌 (30)
참고문헌 신청
윤형주 / 2016 / A Criticality Analysis of the GBC-32 Dry Storage Cask with Hanbit Nuclear Power Plant Unit 3 Fuel Assemblies from the Viewpoint of Burnup Credit / Nuclear Engineering and Technology 48(3):624~634
R. Poskas / 2019 / Modeling of decay heat removal from CONSTOR RMBK-1500 casks during long-term storage of spent nuclear fuel / Energy 170:978~985
H. S. Yoo / 2019 / Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas / Ann. Nucl. Energy 132:108~118
D. Price / 2019 / Advanced BWR criticality safety part II: cask criticality, burnup credit, sensitivity, and uncertainty analyses / Prog. Nucl. Energy 115:126~139
A. Mohammadi / 2016 / Shielding calculation and criticality safety analysis of spent fuel transportation cask in research reactors / Appl. Radiat. Isot 108:129~132
R. Poskas / 2019 / Modeling of decay heat removal from CONSTOR RMBK-1500 casks during long-term storage of spent nuclear fuel / Energy 170:978~985
H. S. Yoo / 2019 / Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas / Ann. Nucl. Energy 132:108~118
D. Price / 2019 / Advanced BWR criticality safety part II: cask criticality, burnup credit, sensitivity, and uncertainty analyses / Prog. Nucl. Energy 115:126~139
A. Mohammadi / 2016 / Shielding calculation and criticality safety analysis of spent fuel transportation cask in research reactors / Appl. Radiat. Isot 108:129~132
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