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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 18 - 24 (7page)
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초록· 키워드
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This study proposes a new method of analyzing the burnup credit in boiling water reactor spent fuelassemblies against various operating parameters. The operating parameters under investigation includefuel temperature, axial burnup profile, axial moderator density profile, and control blade usage. Inparticular, the effects of variations in one and two operating parameters on the curve of effectivemultiplication factor ðkeff Þ versus burnup ðBÞ are, respectively, the so-called single and compound effects. All the calculations were performed using SCALE 6.1 together with the Evaluated Nuclear Data Files, partB (ENDF/B)-VII238-neutron energy group data library. Furthermore, two geometrical models wereestablished based on the General Electric (GE)14 10 10 boiling water reactor fuel assembly and theGeneric Burnup-Credit (GBC)-68 storage cask. The results revealed that the curves of keff versus B, due tosingle and compound effects, can be approximated using a first degree polynomial of B. However, thereactivity deviation (or changes of keff ; Dk) in some compound effects was not a summation of the allDk resulting from the two associated single effects. This phenomenon is undesirable because it may tosome extent affect the precise assessment of burnup credit. In this study, a general formula was thusproposed to express the curves of keff versus B for both single and compound effects.
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참고문헌 (12)
참고문헌 신청
D.E. Mueller / 2012 / Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit, NUREG/CR-7157, ORNL/TM-2012/96
D.E. Mueller / 2012 / Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel, NUREG/CR-7158, ORNL/TM-2016/261
W.(B.J.) Marshall / 2015 / Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems, NUREG/CR-7194, ORNL/ TM-2014/240
G. You / 2012 / Introduction of burn-up credit in nuclear criticality safety analysis / Proc. Eng. 43:297~301
J.C. Wagner / 2000 / Investigation of Burnup Credit Modeling Issues Associated with BWR Fuel, ORNL/TM-1999/193
D.E. Mueller / 2012 / Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel, NUREG/CR-7158, ORNL/TM-2016/261
W.(B.J.) Marshall / 2015 / Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems, NUREG/CR-7194, ORNL/ TM-2014/240
G. You / 2012 / Introduction of burn-up credit in nuclear criticality safety analysis / Proc. Eng. 43:297~301
J.C. Wagner / 2000 / Investigation of Burnup Credit Modeling Issues Associated with BWR Fuel, ORNL/TM-1999/193
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