生产99mo放射性核素用rsg -气体反应器辐照低浓缩铀电镀靶的中子分析

S. Pinem, T. M. Sembiring, T. Tukiran, Ik Iman Kuntoro
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引用次数: 2

摘要

RSG-GAS反应堆是供放射性同位素生产、中子活化分析、研究材料试验、工业需求、科研机构和高校使用的研究型反应堆。RSG-GAS反应堆运行的常规活动之一是将低浓铀目标照射到堆芯中以产生99Mo放射性核素。靶体插入堆芯会改变堆芯的中子特性,使其超过反应堆运行的安全极限。本文分析了低浓铀电镀靶材插入堆芯辐照装置后产生的中子参数。低浓铀电镀辐照靶的中子参数优化对反应堆的安全运行具有重要意义。中子参数计算使用常规用于RSG-GAS核心计算的WIMS/D5和Batan-3DIFF代码进行。通过计算,在36 g的CIP照射位置照射低浓铀电镀靶,其反应性变化为597.724 pcm,最大径向功率峰值因子为1.3078。这两个量都在反应堆运行安全允许的范围内。
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NEUTRONIC ANALYSIS ON IRRADIATION OF THE LEU ELECTROPLATING TARGET IN THE RSG-GAS REACTOR FOR PRODUCTION OF 99MO RADIONUCLIDE
RSG-GAS reactor is a research reactor operated for radioisotope production, neutron activation analysis, research material testing, industry demand, R & D institutions and universities. One of the routine activities performed for RSG-GAS reactor operation is irradiation of LEU targets into the core to produce 99Mo radionuclide. The target insertion in the core will change the neutronic characteristic of the core so it can exceed the safety limits of reactor operation. This paper analyzes the neutronic parameters due to the insertion of the LEU electroplating target into the reactor core irradiation facility. The neutronic parameters for optimizing the LEU electroplating irradiated target are important for the safety of the reactor operation. Neutronic parameter calculations were performed using WIMS/D5 and Batan-3DIFF codes routinely used for RSG-GAS core calculations. Based on calculations by irradiating the LEU electroplating target in a CIP irradiation position of 36 g causes a reactivity change of 597.724 pcm and a maximum radial power peaking factor of 1.3078. Both of these quantities are within the limits permitted for the safety of the reactor operation.
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