Study of circulating liquid fuel in a 1D critical system with thermal feedback

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mathis Caprais , Daniele Tomatis , André Bergeron
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引用次数: 0

Abstract

This research focuses on the description and modeling of a one-dimensional molten salt reactor (MSR), in the presence of thermal feedback. Following the example of previous works, a simple one-dimensional system is proposed, describing a molten salt reactor with a main neutron-multiplying zone called core and a recirculation loop where the salt cools down. Specific attention is paid to the precursors’ drift by modifying the neutron balance equation. Liquid nuclear fuels are characterized by a high volumetric expansion coefficient in comparison to customary solid fuels. Therefore, a strong coupling between neutronics and thermal-hydraulics is expected. As a consequence, a highly negative density coefficient characterizes the thermal feedback on the neutron reactivity. The precursor equation is here inverted analytically and combined with the neutron balance equation to obtain a generalized eigenvalue problem with the neutron flux distribution as the unknown. The balance equations are derived by finite volume integration over a discretized mesh, and the coupling between the two physical models is treated by Picard iterations. The numerical solution is finally extended to time-dependent calculations and compared to an analytical work for a one-dimensional circulating fuel reactor already existing in the literature.
带有热反馈的一维临界系统中的循环液体燃料研究
这项研究的重点是在存在热反馈的情况下,对一维熔盐反应堆(MSR)进行描述和建模。借鉴前人的研究成果,我们提出了一个简单的一维系统,描述了一个熔盐反应堆,它有一个被称为堆芯的主中子增殖区和一个盐冷却的再循环回路。通过修改中子平衡方程,对前驱体漂移给予了特别关注。与常见的固体燃料相比,液体核燃料具有体积膨胀系数高的特点。因此,预计中子学和热力学之间会有很强的耦合。因此,高负密度系数是中子反应性热反馈的特征。在这里,前体方程被反演分析,并与中子平衡方程相结合,从而得到一个以中子通量分布为未知数的广义特征值问题。平衡方程是通过离散网格上的有限体积积分得出的,两个物理模型之间的耦合是通过皮卡尔迭代处理的。最后将数值解决方案扩展到随时间变化的计算,并与文献中已有的一维循环燃料反应堆的分析工作进行比较。
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
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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