Analysis of variation minor actinide pin configurations Np-237, AM-241, and Cm-244 in UN-PuN fueled pressurized water reactor

Ratna Dewi Syarifah, Muhammad Nasrullah, Fajri Prasetya, Ahmad Muzaki Mabruri, A. Arkundato, G. Jatisukamto, Septy Handayani
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Abstract

Actinide minor is a reactor waste with high toxicity and a long half-life. Minor actinides can be reduced by reusing them as fuel mixtures in reactors. This research uses PWR reactors with the primary fuel UN-PuN or Uranium Plutonium Nitride with a burning time of 5 years. The fuel consists of enriched Uranium, reactor-grade Plutonium from LWR waste, and minor actinides including Neptunium-237, Americium-241, and Curium-244. The purpose of this study was to find a design that is effective in reducing minor actinide waste. There are six designs or cases used in the addition of minor actinides. Each case has six minor actinide pins in each assembly. The addition of minor actinides is arranged in heterogeneous cores. The analysis was carried out by observing the values of k-eff, excess reactivity, and mass of minor actinides obtained from simulations using OpenMC code 0.13.2 and the ENDF/B-VIII library. The homogeneous core obtained an excess reactivity of 9.7 % with a percentage of plutonium of 8 %. The results of the homogeneous core are used as a reference for preparing a heterogeneous core. The heterogeneous core obtained an excess reactivity of 9.9 % with a percentage of plutonium F1: 5.5 %, F2: 8 %, and F3: 10.5 %. Np-237 can be reduced by 53 kg, and Am-241 can be reduced by 61 kg with minor actinide pins in case 1. Cm-244 can be reduced by 363 kilograms with minor actinide pins in case 6. Excess reactivity in the addition of Np-237 and Am-241 decreased to 5.3 %, while the accumulation of Cm-244 increased to 12.1 %.
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分析 UN-PuN 燃料压水反应堆中 Np-237、AM-241 和 Cm-244 等次要锕系元素引脚构型的变化
微量锕系元素是一种反应堆废物,具有毒性高和半衰期长的特点。可以通过在反应堆中重新使用次要锕系元素作为燃料混合物来减少次要锕系元素的产生。这项研究使用压水堆反应堆,其主燃料为燃烧时间为 5 年的 UN-PuN 或氮化钚铀。这种燃料由浓缩铀、从低功率堆废料中提取的反应堆级钚以及包括镎237、镅241和锔244在内的次要锕系元素组成。这项研究的目的是找到一种能够有效减少次锕系元素废料的设计。有六种设计或情况被用于添加次锕系元素。每种情况的每个组件中都有六个小锕系元素引脚。次锕系元素的添加被安排在异质磁芯中。分析是通过观察使用 OpenMC 代码 0.13.2 和 ENDF/B-VIII 库模拟获得的 k-eff、过量反应性和次锕系元素质量值进行的。均质堆芯的过量反应率为 9.7%,钚的比例为 8%。均质堆芯的结果可作为制备异质堆芯的参考。异质堆芯的过量反应率为 9.9%,钚的百分比分别为 F1:5.5%、F2:8% 和 F3:10.5%。在情况 1 中,Np-237 可减少 53 千克,Am-241 可减少 61 千克,锕系元素引脚较少。在情况 6 中,使用次要锕系元素栓可将 Cm-244 减少 363 千克。添加 Np-237 和 Am-241 时的反应过剩率下降到 5.3%,而 Cm-244 的累积率上升到 12.1%。
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来源期刊
EUREKA: Physics and Engineering
EUREKA: Physics and Engineering Engineering-Engineering (all)
CiteScore
1.90
自引率
0.00%
发文量
78
审稿时长
12 weeks
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