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
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The burnup profile of spent fuel should be determined accurately for the safety storage ofspent fuel. In this study, a neutron detection system was developed as a part of basic research to analyzethe burnup profile of spent fuel, and a performance was evaluated using a radiation source. The prototypeof the neutron detection system was based on a 3He proportional chamber. The 3He proportional chamberis often used for neutron measurement and analysis because of its high neutron detection efficiency andsimplicity for gamma ray rejection. For quantitative evaluation, tests were conducted using calibrated 252Cfand 137Cs sources. In the performance evaluation, a field applicability was verified by analyzing the detectioncharacteristics according to the nuclide.
Abstract
The burnup profile of spent fuel should be determined accurately for the safety storage ofspent fuel. In this study, a neutron detection system was developed as a part of basic research to analyzethe burnup profile of spent fuel, and a performance was evaluated using a radiation source. The prototypeof the neutron detection system was based on a 3He proportional chamber. The 3He proportional chamberis often used for neutron measurement and analysis because of its high neutron detection efficiency andsimplicity for gamma ray rejection. For quantitative evaluation, tests were conducted using calibrated 252Cfand 137Cs sources. In the performance evaluation, a field applicability was verified by analyzing the detectioncharacteristics according to the nuclide.
참고문헌 (6)
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