开放水平产中子靶中自然对流与衰变热源的研究

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-12 DOI:10.1016/j.nucengdes.2024.113781
Jianfei Tong , Jiahui Chen , Shenqiang Wei , Songlin Wang , Fei Shen , Youlian Lu , Ruiqiang Zhang , Congju Yao , Wen Yin , Tianjiao Liang
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引用次数: 0

摘要

研究了在靶体复杂的流道内由衰减热源引起的自然对流换热现象。利用流体力学原理和传热数值方法建立了靶体的三维模型。研究重点是在目标复杂流道的密闭空间内发生的微对流和非流动换热现象。进行了与电源故障事件有关的边界条件的模拟,并随后根据实验数据进行了验证。结果表明,压力入口和压力出口边界条件下的温度与实验测量值基本一致,分别为52.7℃和51.5℃,误差小于3%。此外,研究表明,外部环境换热系数对内部温度分布的影响可以忽略不计。本研究为中国散裂中子源(CSNS)Ⅱ升级项目的目标站事故情景评估提供了重要的见解和建议。
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The study of natural convection with decay heat source in an open horizontal neutron production target
The research examines the phenomenon of natural convection heat transfer induced by decay heat sources within the intricate flow channels of the target. A three-dimensional model of the target was developed utilizing principles of fluid dynamics and numerical methods for heat transfer. The research emphasizes the micro-convective and non-flow heat transfer phenomena occurring within the confined spaces of the target’s intricate flow channels. Simulations of boundary conditions pertinent to a power failure incident were conducted and subsequently validated against experimental data. The findings indicated that the temperatures at the pressure inlet and pressure outlet boundary conditions closely aligned with the experimental measurements, recorded at 52.7 ℃ and 51.5 ℃, respectively, with an error margin of less than 3%. Additionally, the investigation revealed that the external surrounding heat transfer coefficient has a negligible effect on the internal temperature distribution. This research offers significant insights and recommendations for assessing accident scenarios at the target station for the China Spallation Neutron Source (CSNS) Ⅱ upgrade project.
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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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