Hai Wang , Qinglong Wen , Zhengang Duan , Zhongkai Mei
{"title":"实现高燃耗燃料棒高温辐照的陶瓷气隙热障的渐进多物理场分析","authors":"Hai Wang , Qinglong Wen , Zhengang Duan , Zhongkai Mei","doi":"10.1016/j.nucengdes.2025.114536","DOIUrl":null,"url":null,"abstract":"<div><div>To address the irradiation testing requirements of high-temperature high-burnup fuel rods (HT-HBFR) in low-temperature, low-pressure research reactors, this study proposes an irradiation assembly incorporating a ceramic gas-gap thermal barrier (CGGTB) to mitigate localized overheating in the reactor core. Heat transfer simulations demonstrated that, within a heat flux range of 1,000 ± 200 W/m<sup>2</sup>, the maximum deviation between experimental and theoretical values was –3.76 %, confirming the engineering feasibility of the thermal barrier and it has high predictive accuracy under anticipated operational conditions. Further theoretical calculations, numerical simulations, and hydraulic experiments were conducted to optimize the throttling device geometry and coolant channel parameters. At a target flow rate of 0.854 kg/s, the theoretical pressure drop of the downward coolant flow through the irradiation device exceeded the experimental value by 9.46 %. Progressive multiphysics simulations systematically validated the decoupling control capability of the CGGTB over fuel pellet temperature, cladding surface temperature, and coolant interface temperature. Under a rated heat flux of 1,000 kW/m<sup>2</sup>, the maximum fuel pellet temperature reached 1,259 ℃ and the cladding surface temperature was 615 ℃, both satisfying the test requirements, while the coolant outlet temperature remained at 53.3 ℃, well below the thermal safety limit (195 ℃) of the High Flux Engineering Test Reactor (HFETR). This irradiation strategy provides high-precision technical support for the performance verification of HT-HBFR in non-prototype reactor environments.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114536"},"PeriodicalIF":2.1000,"publicationDate":"2025-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Progressive Multiphysics analysis to Implement a ceramic gas gap thermal barrier Enabling High-Temperature irradiation of High-Burnup fuel rods\",\"authors\":\"Hai Wang , Qinglong Wen , Zhengang Duan , Zhongkai Mei\",\"doi\":\"10.1016/j.nucengdes.2025.114536\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>To address the irradiation testing requirements of high-temperature high-burnup fuel rods (HT-HBFR) in low-temperature, low-pressure research reactors, this study proposes an irradiation assembly incorporating a ceramic gas-gap thermal barrier (CGGTB) to mitigate localized overheating in the reactor core. Heat transfer simulations demonstrated that, within a heat flux range of 1,000 ± 200 W/m<sup>2</sup>, the maximum deviation between experimental and theoretical values was –3.76 %, confirming the engineering feasibility of the thermal barrier and it has high predictive accuracy under anticipated operational conditions. Further theoretical calculations, numerical simulations, and hydraulic experiments were conducted to optimize the throttling device geometry and coolant channel parameters. At a target flow rate of 0.854 kg/s, the theoretical pressure drop of the downward coolant flow through the irradiation device exceeded the experimental value by 9.46 %. Progressive multiphysics simulations systematically validated the decoupling control capability of the CGGTB over fuel pellet temperature, cladding surface temperature, and coolant interface temperature. Under a rated heat flux of 1,000 kW/m<sup>2</sup>, the maximum fuel pellet temperature reached 1,259 ℃ and the cladding surface temperature was 615 ℃, both satisfying the test requirements, while the coolant outlet temperature remained at 53.3 ℃, well below the thermal safety limit (195 ℃) of the High Flux Engineering Test Reactor (HFETR). This irradiation strategy provides high-precision technical support for the performance verification of HT-HBFR in non-prototype reactor environments.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114536\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-10-10\",\"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/S0029549325007137\",\"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/S0029549325007137","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}
Progressive Multiphysics analysis to Implement a ceramic gas gap thermal barrier Enabling High-Temperature irradiation of High-Burnup fuel rods
To address the irradiation testing requirements of high-temperature high-burnup fuel rods (HT-HBFR) in low-temperature, low-pressure research reactors, this study proposes an irradiation assembly incorporating a ceramic gas-gap thermal barrier (CGGTB) to mitigate localized overheating in the reactor core. Heat transfer simulations demonstrated that, within a heat flux range of 1,000 ± 200 W/m2, the maximum deviation between experimental and theoretical values was –3.76 %, confirming the engineering feasibility of the thermal barrier and it has high predictive accuracy under anticipated operational conditions. Further theoretical calculations, numerical simulations, and hydraulic experiments were conducted to optimize the throttling device geometry and coolant channel parameters. At a target flow rate of 0.854 kg/s, the theoretical pressure drop of the downward coolant flow through the irradiation device exceeded the experimental value by 9.46 %. Progressive multiphysics simulations systematically validated the decoupling control capability of the CGGTB over fuel pellet temperature, cladding surface temperature, and coolant interface temperature. Under a rated heat flux of 1,000 kW/m2, the maximum fuel pellet temperature reached 1,259 ℃ and the cladding surface temperature was 615 ℃, both satisfying the test requirements, while the coolant outlet temperature remained at 53.3 ℃, well below the thermal safety limit (195 ℃) of the High Flux Engineering Test Reactor (HFETR). This irradiation strategy provides high-precision technical support for the performance verification of HT-HBFR in non-prototype reactor environments.
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.