Monte Carlo based absolute efficiency calibration of power reactor spent fuel NDA measurements

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-10-08 DOI:10.1016/j.anucene.2024.110953

Péter Kirchknopf , Zoltán Kató , Csongor Kristóf Szarvas , Péter Völgyesi , Imre Szalóki

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引用次数: 0

Abstract

Experiments have been carried out at Paks Nuclear Power Plant for the purpose of spent fuel burnup characterization using gamma-ray spectrometry. Obtaining absolute quantitative information, e.g. fission product activities, from the spectra requires accurate knowledge of the detection efficiency. Due to nature of the measurement conditions, experimental calibration was unfeasible, and the Monte Carlo particle transport method was selected to calculate the efficiency. The model building process is presented, which involves X-ray radiography of the germanium detector, optimization of the dead layer on the outside of the crystal, and a solution to the challenging low-efficiency simulation problem. The simulations were validated using measurements carried out at the Paks reactor units together with verified experimental data from the SFCOMPO library. The constructed model proved to be accurate to the results determined by empirical methods within ±3 % error, promising to be a reliable basis for future applications that require spent fuel characterization.

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基于蒙特卡洛的动力堆乏燃料 NDA 测量绝对效率校准

帕克斯核电厂利用伽马射线光谱仪进行了乏燃料燃烧特性分析实验。要从光谱中获得绝对的定量信息，例如裂变产物活度，就必须准确了解探测效率。由于测量条件的性质，实验校准是不可行的，因此选择了蒙特卡罗粒子传输方法来计算效率。本文介绍了模型的建立过程，包括锗探测器的 X 射线放射成像、晶体外部死层的优化，以及具有挑战性的低效率模拟问题的解决方案。利用在帕克斯反应堆单元进行的测量结果以及 SFCOMPO 数据库中经过验证的实验数据对模拟进行了验证。事实证明，所构建的模型与经验方法确定的结果准确度在 ±3 % 的误差范围内，有望成为未来需要乏燃料特征描述的应用的可靠基础。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.