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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.10
- 수록면
- 3,127 - 3,132 (6page)
- DOI
- https://doi.org/10.1016/j.net.2021.04.013
이용수
초록· 키워드
오류제보하기
Feasibility study of burn-up analysis and monitoring using delayed fast neutrons was investigated atMissouri University of Science and Technology Reactor (MSTR). Burnt and fresh fuel elements were usedto collect delayed fast neutron data for different power levels. Total reactivity varied depending on theburn-up rate of fuel elements for each core configuration. The regulating rod worth was 2.07E-04 Dk/k/inand 1.95E-04 Dk/k/in for T121 and T122 core configurations at 11 inch, respectively. Delayed fast neutronspectrum of F1 (burnt) and F16 (fresh) fuel elements were analyzed further, and a strong correlation wasobserved between delayed fast neutron emission and burn-up. According to the analyzed peaks in burntand fresh fuels, reactor power dependency was observed and it was determined that delayed neutronprovided more reliable results at reactor powers of 50 kW and above.
목차
등록된 정보가 없습니다.
참고문헌 (34)
참고문헌 신청
C. Willman / 2006 / A non-destructive method for discriminating MOX fuel from LEU fuel for safeguards purpose / Ann. Nucl. Energy 33:766~773
M. L. Dennis / 2010 / Feasibility of 106Ru peak measurement for MOX fuel burn-up analysis / Nucl. Eng. Des 240
C. Riffard / 2006 / MOX fuel characterization for burnup credit application : extension of non-destructive method qualified for LEU fuels / Nucl. Technol 154:186~193
C. Willman / 2006 / Non-destructive assay of spent nuclear fuel with gamma-ray spectroscopy" / Ann. Nucl. Energy 33:427~438
T. Akyurek / 2015 / Spent fuel interrogation using delayed fast neutron spectrum at Missouri University of Science and Technology Reactor / Prog. Nucl. Energy 85:525~540
M. L. Dennis / 2010 / Feasibility of 106Ru peak measurement for MOX fuel burn-up analysis / Nucl. Eng. Des 240
C. Riffard / 2006 / MOX fuel characterization for burnup credit application : extension of non-destructive method qualified for LEU fuels / Nucl. Technol 154:186~193
C. Willman / 2006 / Non-destructive assay of spent nuclear fuel with gamma-ray spectroscopy" / Ann. Nucl. Energy 33:427~438
T. Akyurek / 2015 / Spent fuel interrogation using delayed fast neutron spectrum at Missouri University of Science and Technology Reactor / Prog. Nucl. Energy 85:525~540
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