fcm燃料微气冷堆多物理场耦合分析方法的建立

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Kuaiyuan Feng , Qufei Song , Yihu Wang , Hui Guo , Tenglong Cong , Yao Xiao , Hanyang Gu
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引用次数: 0

摘要

目前,具有随机分散三结构各向同性(TRISO)颗粒的全陶瓷微封装(FCM)燃料在气冷微堆中得到了广泛应用。气冷微堆体积有限,结构复杂,堆芯内部多物理场紧密耦合,给多物理场分析带来了挑战。在多物理场面向对象仿真环境(MOOSE)框架下,开发并验证了一种基于多物理场耦合的fcm燃料微气冷堆分析方法。燃料组件计算结果表明,在不同温度点生成的多组截面(MGXS)具有较高的计算精度。MOC-MOOSE计算结果在温度场、功率分布和温度场方面具有较高的计算精度。同时,MOC-MOOSE方法的计算成本仅为基准求解器的10%,显示出较高的计算效率。最后进行了全芯多物理场耦合。得到了三维针脚间的燃料功率分布,最大功率发生在轴向活动区中间平面的外围燃料组件的最外层燃料棒。燃料、基质和冷却剂的最高温度分别为1698 K、1206 K和1002 K。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor
At present, Fully Ceramic Microencapsulated (FCM) fuel with randomly dispersed tri-structural isotropic (TRISO) particles is widely used in gas-cooled microreactors. Gas-cooled microreactors usually exhibit limited volume and complex structure, with tightly coupled multi-physical fields inside the core, presenting challenges for multiphysics analysis. In this work, a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor within the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework is developed and verified. The fuel assembly calculation results show that the generated multi-group cross-section (MGXS) at different temperature points exhibits high computational accuracy. The MOC-MOOSE results exhibit a high computational accuracy in keff, power distribution, and temperature field. Meanwhile, the calculation cost for the MOC-MOOSE method is only 10 % of that required by the benchmark solver, demonstrating high computational efficiency. At last, the full-core multiphysics coupling was conducted. The three-dimensional pin-by-pin fuel power distribution was obtained, with the highest power occurring in the outermost fuel rods of the peripheral fuel assemblies at the middle plane of the axial active region. The maximum fuel, matrix, and coolant temperatures are 1698 K, 1206 K, and 1002 K, separately.
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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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