방사선산업학회지 (Journal of Radiation Industry)

한국방사선산업학회 (Korean Society of Radiation Industry)
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사용후핵연료 연소도 측정을 위한 감마선 검출기의 분광특성 연구

Spectroscopic Properties of Gamma-ray Detector to Measure the Burnup of Spent Nuclear Fuel

  • 투고 : 2023.02.17
  • 심사 : 2023.03.22
  • 발행 : 2023.03.31
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초록

Burnup of spent nuclear fuel should be determined accurately for the safety storage of spent nuclear fuel. In this study, a gamma detection system was developed as a part of basic research to measure the burnup of spent nuclear fuel, and its performance was evaluated using a calibration source. The prototype of the gamma detection system was based on a semiconductor sensor using a CZT (Cadmium Zinc Telluride). For quantitative evaluation, tests were conducted using 137Cs, 134Cs and 252Cf calibration source. In the performance evaluation, Its field applicability was verified by assessing the energy resolution, the detection linearity and the shielding attenuation 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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