{"title":"辐照碳化硅热导率和体积膨胀的计算框架","authors":"Daxi Guo, Hengfeng Gong, Mingzhou Chen, Yinghong Chen, Shihuai Wang, Jianhan Zhai, Xiansheng Zhang, Yan Yan, Zhiwei Lu, Jiwei Wang, Jiaxiang Xue, Yehong Liao, Guoliang Zhang","doi":"10.1016/j.nucengdes.2025.114073","DOIUrl":null,"url":null,"abstract":"<div><div>Defect production and accumulation in SiC has been studied by molecular dynamics (MD) simulations, and a kinetic model has been developed for defect evolution in SiC in the temperature regime of 473 K to 1073 K. Simulations show that the increase in irradiation temperature diminishes the defect production efficiency of SiC and suppresses the defect accumulation. Thermal conductivity and swelling calculated by the model show good agreement with isothermal irradiation experiments. Evolution of thermal conductivity and swelling under varying temperature shows that the current model can overcome the drawback of isothermal models in terms of unphysical concurrent evolution with temperature during short transient. Thermo-mechanical analysis of SiC cladding under typical LWR loading conditions reveals that the proposed model and the existing models predict similar stress distribution and evolution under steady power, while the stress is underestimated during reactor shutdown/power ramp-down and overestimated during power ramp-up by the previous isothermal model. The results indicate that the proposed model can be applied to the fuel performance analysis especially for cases with abrupt temperature changes such as reactor shutdown and power ramp.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"438 ","pages":"Article 114073"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Computational framework for thermal conductivity and volumetric swelling of irradiated silicon carbide\",\"authors\":\"Daxi Guo, Hengfeng Gong, Mingzhou Chen, Yinghong Chen, Shihuai Wang, Jianhan Zhai, Xiansheng Zhang, Yan Yan, Zhiwei Lu, Jiwei Wang, Jiaxiang Xue, Yehong Liao, Guoliang Zhang\",\"doi\":\"10.1016/j.nucengdes.2025.114073\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Defect production and accumulation in SiC has been studied by molecular dynamics (MD) simulations, and a kinetic model has been developed for defect evolution in SiC in the temperature regime of 473 K to 1073 K. Simulations show that the increase in irradiation temperature diminishes the defect production efficiency of SiC and suppresses the defect accumulation. Thermal conductivity and swelling calculated by the model show good agreement with isothermal irradiation experiments. Evolution of thermal conductivity and swelling under varying temperature shows that the current model can overcome the drawback of isothermal models in terms of unphysical concurrent evolution with temperature during short transient. Thermo-mechanical analysis of SiC cladding under typical LWR loading conditions reveals that the proposed model and the existing models predict similar stress distribution and evolution under steady power, while the stress is underestimated during reactor shutdown/power ramp-down and overestimated during power ramp-up by the previous isothermal model. The results indicate that the proposed model can be applied to the fuel performance analysis especially for cases with abrupt temperature changes such as reactor shutdown and power ramp.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"438 \",\"pages\":\"Article 114073\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-04-17\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S002954932500250X\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002954932500250X","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}
Computational framework for thermal conductivity and volumetric swelling of irradiated silicon carbide
Defect production and accumulation in SiC has been studied by molecular dynamics (MD) simulations, and a kinetic model has been developed for defect evolution in SiC in the temperature regime of 473 K to 1073 K. Simulations show that the increase in irradiation temperature diminishes the defect production efficiency of SiC and suppresses the defect accumulation. Thermal conductivity and swelling calculated by the model show good agreement with isothermal irradiation experiments. Evolution of thermal conductivity and swelling under varying temperature shows that the current model can overcome the drawback of isothermal models in terms of unphysical concurrent evolution with temperature during short transient. Thermo-mechanical analysis of SiC cladding under typical LWR loading conditions reveals that the proposed model and the existing models predict similar stress distribution and evolution under steady power, while the stress is underestimated during reactor shutdown/power ramp-down and overestimated during power ramp-up by the previous isothermal model. The results indicate that the proposed model can be applied to the fuel performance analysis especially for cases with abrupt temperature changes such as reactor shutdown and power ramp.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.