考虑白垩河未识别沉积层的(UN + U3Si2)-SiC体系亚通道热水力分析

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-05-07 DOI:10.1016/j.nucengdes.2025.114126

Mingdong Kai , Jiejin Cai

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引用次数: 0

摘要

（UN + U3Si2）-SiC燃料包壳组合是最有潜力的耐事故燃料包壳组合之一。本文考虑了表面结垢对堆芯传热的影响，分析了稳态工况和典型LOFA事故工况下耐事故燃料(UN + U3Si2)-SiC燃料包壳组合的热工特性。首先，通过PSBT（PWR Subchannel and Bundle Test）基准实验对本文构建的模型进行了系统验证。然后，通过分析(UN + U3Si2)-SiC燃料包壳组合的热物理性质，进一步探讨了存在CRUD （Chalk River unknown Deposits）和不同厚度时稳态和瞬态工况下的热参数变化。最后，分析了LOFA事故中考虑包层腐蚀的安全准则参数，并对堆芯安全性进行了判断。结果表明：堆芯的存在会增加堆芯的MFCT和MCT，使堆芯的传热恶化。CRUD越厚，传热劣化程度越高。CRUD的存在也会降低堆芯安全运行参数MDNBR（最小偏离核沸腾比），但由于事故容忍燃料(UN + U3Si2)-SiC燃料包壳组合的优越性能，CRUD对堆芯安全运行的影响仍在可控范围内。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Subchannel thermal–hydraulic analysis of (UN + U3Si2)-SiC system considering Chalk River Unidentified deposits layer

The (UN + U₃Si₂)-SiC fuel-cladding combination is one of the most potential accident-tolerant fuel-cladding combinations. In this paper, the influence of surface fouling on core heat transfer is considered, and the thermal–hydraulic characteristics of the accident tolerant fuel (UN + U₃Si₂)-SiC fuel-cladding combination under steady-state conditions and typical LOFA accident conditions are analyzed. Firstly, the model constructed in this paper is systematically validated through PSBT(PWR Subchannel and Bundle Test) benchmark experiments. Then the variation of thermal parameters under steady-state and transient operating conditions when CRUD (Chalk River Unidentified Deposits) is present and at different thicknesses is further explored by analyzing the thermophysical properties of the (UN + U₃Si₂)-SiC fuel-cladding combination. Finally, the safety criterion parameters considering cladding corrosion during LOFA accident are analyzed, and the core safety is judged. The results show that the presence of CRUD will increase the MFCT and MCT of the reactor core and deteriorate the heat transfer. And the thicker the CRUD, the higher the degree of heat transfer deterioration. The existence of CRUD will also reduce the core safe operation parameter MDNBR (Minimal departure from nuclear boiling ratio), but due to the superior performance of the accident tolerant fuel (UN + U₃Si₂)-SiC fuel-cladding combination, the impact of CRUD on the core safe operation is still within the controllable range.

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来源期刊

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.