中子活化程序ABURN在核装置停堆剂量率计算中的应用研究
Application Research of Neutron Activation Code ABURN in Shutdown Dose Rate Calculation of Nuclear Installation
摘要: 在核装置中，活化区产生的大量中子导致装置内的材料活化严重，停堆后装置周围的放射性水平依然较强，为装置的维修维护带来了困难。分析核装置中放射性核素的活度、衰变热、光子剂量等参数是屏蔽计算中不可或缺的工作，同时精确的活化计算和停堆后的光子剂量计算，对于核装置检修和人员辐射安全也有非常重要的意义。ABURN程序是由华北电力大学核设施源项研究组自主研发的中子活化计算程序，可以进行活化计算、衰变计算、不确定性和敏感性分析、核素径迹追踪和贡献统计，可以输出多种工况下的核素原子数量、质量、活度、衰变热、γ谱等关键参数。本文基于国际上主流的停堆剂量率计算方法——严格两步法(R2S)，实现了自主化活化程序ABURN和蒙卡程序MCNP的耦合，开发了中子输运计算、材料活化计算和光子输运计算的自动耦合接口程序，进而得到核装置周围的停堆剂量率分布。本文利用ITER-T426实验装置模型进行基准验证，将ABURN程序计算结果与FISPACT程序计算结果以及实验测量结果进行了对此，结果一致性较好，表明了ABURN程序在核装置停堆剂量率计算中的可用性。
Abstract: In nuclear devices, the large number of neutrons produced by the core leads to severe activation of the materials in the device, and the radioactivity level around the device remains high after the reactor shutdown, making it difficult for the maintenance of the device. The analysis of activation problems such as activity, decay heat and photon dose of radionuclides in fusion devices is an indispensable study in shielding calculations, and accurate activation calculations and photon dose calculations after reactor shutdown are also of great importance for reactor maintenance and radiation safety of personnel. ABURN program is an activation calculation program developed by the source project team of North China Electric Power University, which uses TTA and CRAM. It can perform activation calculation, decay calculation, uncertainty and sensitivity analysis, nuclide tracing and pulse calculation, and can output key parameters such as nuclide atomic number, activity, decay heat and γ spectrum under various operating conditions. In this paper, based on the international mainstream dose rate calculation method for deactivation, the rigorous two-step method (R2S), the coupling of the autonomous activation procedure ABURN and Monte Carlo procedure MCNP is realized, and the automatic coupling interface of neutron transport calculation, material activation calculation and photon transport calculation is developed, which leads to the deactivation dose rate distribution around the nuclear device. The results of the ABURN are compared with those of the FISPACT and experimental measurements using the ITER-T426 experimental device model for benchmark validation, and the small deviations are within acceptable limits, the usability of the ABURN program in shutdown dose rate calculate of the deactivation pile is verified.
文章引用：赵晓泽, 张竞宇, 谭琳, 肖懿鑫, 王娟娟, 于虓, 倪王慕鸿. 中子活化程序ABURN在核装置停堆剂量率计算中的应用研究[J]. 核科学与技术, 2023, 11(1): 30-38. https://doi.org/10.12677/NST.2023.111003

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