基于分批燃料后处理方案的小型模块化熔盐反应堆中的钚利用

IF 3.6 1区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Xue-Chao Zhao, Rui Yan, Gui-Feng Zhu, Ya-Fen Liu, Jian Guo, Xiang-Zhou Cai, Yang Zou
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引用次数: 0

摘要

考虑到钍燃料的应用、内在安全性、可持续性和抗扩散性,熔盐反应堆(MSR)具有突出的特点。然而,现阶段裂变材料十分稀缺,因此熔盐堆很难实现纯钍铀燃料循环。因此,使用钚或浓缩铀作为 MSR 的初始燃料更为实际。在本研究中,我们旨在验证利用钚作为初始燃料的小型模块化 MSR(SM-MSR-Pu)的可行性,并强调其优缺点。首先,介绍了 SM-MSR-Pu 的结构设计和燃料管理方案。其次,计算了石墨辐照寿命、燃烧性能和温度反应系数等中子特性,分析了 SM-MSR-Pu 的物理特性。结果表明,钚是 SM-MSR 的一种可行且有利的起始燃料,但仍有一些缺陷需要解决。在 250 MWth SM-MSR-Pu中,大约会产生288.64千克({^{233}\hbox {U}})纯度大于90%的钚,而每十年会燃烧978.00千克。在 50 年的运行时间里,温度反应系数从 \(-4.0\) 下降到 \(-6.5\) pcm K\(^{-1}\) ,从而确保了长期安全运行。然而,钚的数量和微量锕系元素(MAs)的积累会随着燃烧时间的延长而增加,\({^{233}\hbox {U}}\)的年产量和纯度也会下降。为了达到最佳的燃烧性能,最好将整个运行时间设定为 30 年。无论如何,堆芯中最终会积累超过 3600 千克的钚。要有效利用这些积累的钚,还需要进一步的研究。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme

Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme

A molten salt reactor (MSR) has outstanding features considering the application of thorium fuel, inherent safety, sustainability, and resistance to proliferation. However, fissile material \({^{233}\hbox {U}}\) is significantly rare at the current stage, thus it is difficult for MSR to achieve a pure thorium-uranium fuel cycle. Therefore, using plutonium or enriched uranium as the initial fuel for MSR is more practical. In this study, we aim to verify the feasibility of a small modular MSR that utilizes plutonium as the starting fuel (SM-MSR-Pu), and highlight its advantages and disadvantages. First, the structural design and fuel management scheme of the SM-MSR-Pu were presented. Second, the neutronic characteristics, such as the graphite-irradiation lifetime, burn-up performance, and coefficient of temperature reactivity were calculated to analyze the physical characteristics of the SM-MSR-Pu. The results indicate that plutonium is a feasible and advantageous starting fuel for a SM-MSR; however, there are certain shortcomings that need to be solved. In a 250 MWth SM-MSR-Pu, approximately 288.64 kg \({^{233}\hbox {U}}\) of plutonium with a purity of greater than 90% is produced while 978.00 kg is burned every ten years. The temperature reactivity coefficient decreases from \(-4.0\) to \(-6.5\) pcm K\(^{-1}\) over the 50-year operating time, which ensures a long-term safe operation. However, the amount of plutonium and accumulation of minor actinides (MAs) would increase as the burn-up time increases, and the annual production and purity of \({^{233}\hbox {U}}\) will decrease. To achieve an optimal burn-up performance, setting the entire operation time to 30 years is advisable. Regardless, more than 3600 kg of plutonium eventually accumulate in the core. Further research is required to effectively utilize this accumulated plutonium.

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来源期刊
Nuclear Science and Techniques
Nuclear Science and Techniques 物理-核科学技术
CiteScore
5.10
自引率
39.30%
发文量
141
审稿时长
5 months
期刊介绍: Nuclear Science and Techniques (NST) reports scientific findings, technical advances and important results in the fields of nuclear science and techniques. The aim of this periodical is to stimulate cross-fertilization of knowledge among scientists and engineers working in the fields of nuclear research. Scope covers the following subjects: • Synchrotron radiation applications, beamline technology; • Accelerator, ray technology and applications; • Nuclear chemistry, radiochemistry, radiopharmaceuticals, nuclear medicine; • Nuclear electronics and instrumentation; • Nuclear physics and interdisciplinary research; • Nuclear energy science and engineering.
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