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首页> 外文会议>International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications >Burnup measurement of spent fuel assembly by CZT-based gamma-ray spectroscopy for input nuclear material accountancy of pyroprocessing
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Burnup measurement of spent fuel assembly by CZT-based gamma-ray spectroscopy for input nuclear material accountancy of pyroprocessing

机译：基于CZT的伽马射线能谱仪测量乏燃料组件的燃耗，以便进行热加工的输入核材料核算

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Input nuclear material accountancy is crucial for a pyroprocessing facility safeguards. Until a direct Pu measurement technique is established, an indirect method based on code calculations with burnup measurement and neutron counting for 244Cm could be a practical option. Burnup can be determined by destructive analysis (DA) for final dispositive accuracy or by nondestructive assay (NDA) for near-real time accountancy. In the present study, an underwater burnup measurement system based on gamma-ray spectroscopy with the CZT detector was developed and tested on a spent fuel assembly. Burnup was determined according to the 134Cs/137Cs activity ratio with efficiency correction by Geant4 Monte Carlo simulations. The activity ratio as a function of burnup was obtained by ORIGEN calculations. The measured burnup error was 8.6%, which was within the measurement uncertainty. It is expected that the underwater burnup measurement system could fulfill an important role as a means of near-real time accountancy at a future pyroprocessing facility.
机译：投入的核材料核算对于高温处理设施的保障至关重要。在建立直接Pu测量技术之前，基于代码计算的燃尽测量和中子计数 244 Cm的间接方法可能是一种实用的选择。燃耗可以通过破坏性分析（DA）来确定最终的准确性，也可以通过非破坏性分析（NDA）来进行近实时核算。在本研究中，开发了一种基于带有CZT检测器的伽马射线光谱学的水下燃尽测量系统，并在乏燃料组件上进行了测试。根据 134 Cs / 137 Cs活度比确定燃耗，并通过Geant4 Monte Carlo模拟进行效率校正。通过燃耗（ORIGEN）计算获得活性比作为燃耗的函数。测得的燃尽误差为8.6％，在测量不确定度之内。预计水下燃尽测量系统将在未来的高温处理设施中担负起近实时核算的重要作用。

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