사용후핵연료 연소도 측정을 위한 감마선 검출기의 분광특성 연구
Spectroscopic Properties of Gamma-ray Detector to Measure the Burnup of Spent Nuclear Fuel
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초록
Burnup of spent nuclear fuel should be determined accurately for the safety storage ofspent nuclear fuel. In this study, a gamma detection system was developed as a part of basic researchto measure the burnup of spent nuclear fuel, and its performance was evaluated using a calibrationsource. 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 252Cfcalibration source. In the performance evaluation, Its field applicability was verified by assessing theenergy resolution, the detection linearity and the shielding attenuation according to the nuclide.
Abstract
Burnup of spent nuclear fuel should be determined accurately for the safety storage ofspent nuclear fuel. In this study, a gamma detection system was developed as a part of basic researchto measure the burnup of spent nuclear fuel, and its performance was evaluated using a calibrationsource. 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 252Cfcalibration source. In the performance evaluation, Its field applicability was verified by assessing theenergy resolution, the detection linearity and the shielding attenuation according to the nuclide.
참고문헌 (5)
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