방사선산업학회지 (Journal of Radiation Industry)

한국방사선산업학회 (Korean Society of Radiation Industry)
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원전 내 사용후핵연료 연소도 측정을 위한 중성자 검출기의 성능 평가 연구

A Study on Performance Characteristics of Neutron Detector to Measure the Burnup Profile of Spent Fuel in NPP

  • 투고 : 2023.06.30
  • 심사 : 2023.09.06
  • 발행 : 2023.09.30
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초록

The burnup profile of spent fuel should be determined accurately for the safety storage of spent fuel. In this study, a neutron detection system was developed as a part of basic research to analyze the burnup profile of spent fuel, and a performance was evaluated using a radiation source. The prototype of the neutron detection system was based on a 3He proportional chamber. The 3He proportional chamber is often used for neutron measurement and analysis because of its high neutron detection efficiency and simplicity for gamma ray rejection. For quantitative evaluation, tests were conducted using calibrated 252Cf and 137Cs sources. In the performance evaluation, a field applicability was verified by analyzing the detection characteristics according to the nuclide.

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과제정보

본 연구는 한국에너지기술평가원 재원으로, 원전 안전운영을 위한 핵심소재, 부품, 장비 국산화 기술개발사업 '사용후핵연료 연소도 측정 설비 기술개발(과제번호: 20222B10100060)'에 의해 수행되었으며, 그 지원에 감사드립니다.

참고문헌

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