Hydrodynamics coupled circulating-fuel reactor equations in comoving frame and their analytical solutions for molten salt reactors

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Ayhan Yılmazer, Gökhan Pediz
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引用次数: 0

Abstract

Effects of relative motion between moving fuel and neutrons are usually not considered in the analysis of Circulating Fuel Reactors (CFRs). In this study, we formulate neutron transport equation for CFRs in a hydrodynamic representation in terms of velocities relative to moving fuel. Using the P1 approximation in the comoving transport equation, the diffusion equation for CFRs is obtained. Mass transport of precursors is considered in the formulations. Comoving frame CFRs equations are analytically solved for critical slab problem and a closed form criticality condition is obtained. Comoving representation has introduced corrections to Eulerian cross sections arising from the acceleration term. Hydrodynamics coupling has posed density modifications to cross sections. A parametric study of corrective terms is carried out to calculate effects of these corrections on a generic MSR and on Molten Salt Breeder Reactor (MSBR).
移动框架下的水动力学耦合循环燃料反应堆方程及其对熔盐反应堆的解析解
在对循环燃料反应堆(CFR)进行分析时,通常不会考虑运动燃料与中子之间相对运动的影响。在本研究中,我们以相对于运动燃料的速度为基础,用流体力学表示法计算了循环燃料堆的中子输运方程。利用移动输运方程中的 P1 近似,可以得到 CFR 的扩散方程。公式中考虑了前驱体的质量输运。对临界板块问题的移动框架 CFRs 方程进行了分析求解,并得到了闭式临界条件。运动表示法引入了加速项对欧拉截面的修正。流体动力学耦合对横截面提出了密度修正。对修正项进行了参数研究,以计算这些修正对一般 MSR 和熔盐增殖反应堆 (MSBR) 的影响。
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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