Progressive Multiphysics analysis to Implement a ceramic gas gap thermal barrier Enabling High-Temperature irradiation of High-Burnup fuel rods

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Hai Wang , Qinglong Wen , Zhengang Duan , Zhongkai Mei
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Abstract

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.
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
为了解决低温低压研究堆中高温高燃耗燃料棒(HT-HBFR)的辐照测试要求,本研究提出了一种包含陶瓷气隙热障(CGGTB)的辐照组件,以减轻堆芯的局部过热。传热模拟结果表明,在热流密度为1000±200 W/m2的范围内,实验值与理论值的最大偏差为- 3.76%,验证了该热障的工程可行性,在预期运行条件下具有较高的预测精度。通过进一步的理论计算、数值模拟和水力实验,优化了节流装置的几何形状和冷却液通道参数。在目标流量为0.854 kg/s时,辐照装置冷却剂下行流的理论压降比实验值高出9.46%。渐进式多物理场仿真系统地验证了CGGTB对燃料球团温度、包层表面温度和冷却剂界面温度的解耦控制能力。在额定热流密度为1000 kW/m2时,燃料球团最高温度达到1259℃,包壳表面温度达到615℃,均满足试验要求,而冷却剂出口温度保持在53.3℃,远低于高通量工程试验堆(HFETR)的热安全极限(195℃)。该辐照策略为高温高压bfr在非原型堆环境下的性能验证提供了高精度的技术支持。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
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.
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