Coupled Analysis of Thorium-based Fuels in the High-Performance Light Water Reactor Fuel Assembly

IF 0.6 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atom Indonesia Pub Date : 2021-08-10 DOI:10.17146/aij.2021.1081
Y. Pérez, C. R. García, F. Mena, L. Castro
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引用次数: 3

Abstract

One of the six selected concepts to be part of Generation IV nuclear reactors is the Supercritical Light Water Cooled Reactor. The High-Performance Light Water Reactor (HPLWR) is the European version and it is a very promising design. In recent years, interest in the study of thorium-based fuel cycles has been renewed and its possibilities for current LWRs have been evaluated. The use of thorium-based fuels will be fundamental in the future sustainability of nuclear energy, since in addition to its abundance in nature, thorium has an important group of advantages. In this paper, performance of thorium-based fuels in the typical fuel assembly of the HPLWR reactor is evaluated, using a computational model based on CFD and Monte Carlo codes for the neutronic/thermal-hydraulic coupled analysis. The volumetric power density profiles, coolant temperature profiles, fuel temperature profiles and others are compared with those obtained for standard UO 2 fuel. When the thorium-based fuels are used, the obtained infinite multiplication coefficients are smaller than the value obtained when UO 2 is used, since the 232 Th isotope has a lower contribution to the multiplicative properties of the medium than 238 U. As a result, a difference of approximately 12 000 pcm was observed. The results verified that the HPLWR is a thermal reactor with a hard spectrum. There are no notable changes in the neutron spectrum if the mass fraction of thorium is slightly varied. With coupled analysis, the potential benefits of the utilization of thorium-based fuels were verified. Moreover, a significant temperature decrease by 136 K on the center line of the fuel elements was observed. When the mass fraction of thorium increases in the oxides mixture, the weighted average temperature on the fuel elements decreases .
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高性能轻水堆燃料组件中钍基燃料的耦合分析
第四代核反应堆的六个选定概念之一是超临界轻水冷却反应堆。高性能轻水反应堆(HPLWR)是欧洲版本,是一个非常有前途的设计。近年来,人们对钍基燃料循环的研究重新产生了兴趣,并对其在当前LWR中的可能性进行了评估。钍基燃料的使用将是核能未来可持续性的基础,因为除了其在自然界中的丰富性外,钍还有一组重要的优势。本文使用基于CFD和蒙特卡罗程序的计算模型对HPLWR反应堆典型燃料组件中的钍基燃料的性能进行了评估,用于中子/热工水力耦合分析。将体积功率密度曲线、冷却剂温度曲线、燃料温度曲线和其他曲线与标准UO2燃料获得的曲线进行比较。当使用钍基燃料时,获得的无限乘法系数小于使用UO2时获得的值,因为232Th同位素对介质乘法性质的贡献低于238U。因此,观察到大约12000 pcm的差异。结果验证了HPLWR是一个具有硬谱的热反应器。如果钍的质量分数略有变化,中子光谱不会发生显著变化。通过耦合分析,验证了利用钍基燃料的潜在效益。此外,在燃料元件的中心线上观察到显著的温度降低了136K。当氧化物混合物中钍的质量分数增加时,燃料元件的加权平均温度降低。
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
Atom Indonesia
Atom Indonesia NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
0.00%
发文量
20
审稿时长
16 weeks
期刊介绍: The focus of Atom Indonesia is research and development in nuclear science and technology. The scope of this journal covers experimental and analytical research in nuclear science and technology. The topics include nuclear physics, reactor physics, radioactive waste, fuel element, radioisotopes, radiopharmacy, radiation, and neutron scattering, as well as their utilization in agriculture, industry, health, environment, energy, material science and technology, and related fields.
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