Kuaiyuan Feng , Qufei Song , Yihu Wang , Hui Guo , Tenglong Cong , Yao Xiao , Hanyang Gu
{"title":"Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor","authors":"Kuaiyuan Feng , Qufei Song , Yihu Wang , Hui Guo , Tenglong Cong , Yao Xiao , Hanyang Gu","doi":"10.1016/j.net.2025.103645","DOIUrl":null,"url":null,"abstract":"<div><div>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 <em>k</em><sub><em>eff</em></sub>, 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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103645"},"PeriodicalIF":2.6000,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S173857332500213X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
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.
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