Enhancing fuel breed-burn performance in a sodium-cooled fast reactor using a novel reactivity control method

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2024-09-14 DOI:10.1016/j.pnucene.2024.105436
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Abstract

This study aims to enhance the fuel cycle and fissile breeding performance of a sodium-cooled fast breeder reactor (FBR) by utilizing minor actinides (MAs) as a means of reactivity control alongside partially-inserted control rods. Choosing the PFBR-500 as the reference design, four core models, designated as Cases A, B, C, and D, utilizing various proportions of minor actinides (MAs) were built and simulated using OpenMC. The MA concentrations were optimized to compensate for the withdrawal of control rods and ensure the same initial reactivity for all cores. Burnup analysis over 365 EFPDs revealed a significant increase in cycle length and burnup for the modified cores along with a modest rise in breeding ratio. Notably, Case C, employing 3.45 wt.% MAs in the 88 inner-core fuel subassemblies achieved an extra 62.25 EFPDs cycle length, a 33.74% rise in single-cycle burnup, and a 3.86% increase in breeding gain compared to the reference. Loading MAs into the inner-core region proved to be more effective in enhancing both fertile-to-fissile conversion (thus extending the cycle length and fuel burnup) and transmutation than utilizing MAs throughout the core due to greater neutron flux at the core center. While Case D utilizing 2.2 wt.% MAs both in the inner and outer core fuel subassemblies had the highest overall MA loading, it demonstrated lower increments in cycle length, burnup, and breeding gain compared to Case C. Case C also exhibited the highest overall destruction rate (approximately 24%/y) for Np and Am isotopes, and successfully transmuted around 24.08 kg 237Np, 9.33 kg 241Am and 3.82 kg 243Am over the course of a single year. The addition of MAs also achieved a slight flattening of the axial and radial flux profile and a decrease in the flux peaking factor. However, it slightly lowered the beta-effective, Doppler constant, and control rod assembly worth, and shifted the coolant void reactivity worth to the positive side.

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利用新型反应性控制方法提高钠冷快堆的燃料培育-燃烧性能
本研究旨在通过利用次锕系元素(MAs)作为部分插入式控制棒的反应性控制手段,提高钠冷快中子增殖反应堆(FBR)的燃料循环和裂变增殖性能。选择 PFBR-500 作为参考设计,利用 OpenMC 建立并模拟了四个核心模型,分别称为情况 A、B、C 和 D,其中使用了不同比例的次要锕系元素(MAs)。对 MA 浓度进行了优化,以补偿控制棒的退出,并确保所有堆芯具有相同的初始反应性。对 365 个 EFPD 进行的燃耗分析表明,改进后的堆芯的循环长度和燃耗显著增加,育成比也略有上升。值得注意的是,案例 C 在 88 个内核燃料组件中使用了 3.45 wt.% 的 MA,与参考值相比,循环长度增加了 62.25 EFPDs,单循环燃耗增加了 33.74%,育成增益增加了 3.86%。事实证明,由于堆芯中心的中子通量更大,在堆芯内部区域加载 MAs 比在整个堆芯中使用 MAs 更能有效地提高可育到易裂变的转换(从而延长循环长度和燃料燃烧量)和嬗变。虽然在内核和外核燃料组件中都使用了 2.2 重量百分比 MA 的情况 D 具有最高的 MA 总装载量,但与情况 C 相比,它在循环长度、燃耗和繁殖增益方面的增量较低。情况 C 还显示出最高的 Np 和 Am 同位素总销毁率(约 24%/年),并在一年内成功嬗变了约 24.08 千克 237Np、9.33 千克 241Am 和 3.82 千克 243Am。添加 MAs 还使轴向和径向通量曲线略微变平,并降低了通量峰值因数。不过,它略微降低了β-有效值、多普勒常数和控制棒组件值,并使冷却剂空隙反应性值向正值偏移。
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
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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