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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2024.9
- 수록면
- 249 - 253 (5page)
- DOI
- 10.23042/radin.2024.18.3.249
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초록· 키워드
오류제보하기
For the safe management and disposal of spent fuel, it is essential to accurately determine the quan tities of nuclides present within the spent fuel. In this study, a Gamma/Neutron detection system was developed asa part of basic research to measure the burnup profile of spent fuel, and a performance was evaluated using majornuclides. The prototype of the Gamma/Neutron detection system consisted of a CZT sensor and a 3He chamber. Forquantitative evaluation, studies were conducted using calibrated 137Cs, 134Cs, 154Eu and 252Cf sources. In the perfor mance evaluation, a field applicability was verified by analyzing the detection characteristics according to the nuclide.
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