碎屑床重熔过程传热特性的实验研究

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Lijun Jian , Xiao Zeng , Peng Yu , Yidan Yuan
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引用次数: 0

摘要

IVR (in - vessel Retention)的研究主要集中在稳态熔池中的自然对流。然而,从颗粒碎屑床熔融到熔池的动态过程也是至关重要的。碎屑层重熔过程可能表现出可能超过稳态热负荷的中间状态,同时作为稳态熔池的初始条件。本研究利用coremt - ht实验设备对单组分和双组分碎屑床重熔过程进行了实验研究。结果包括现象学特征、温度演变和热通量分布。在两个实验中,均未观察到超过终态的瞬态热通量。值得注意的是,在熔池壁上观察到的两层壳层与传统的单氧化壳稳态熔池形态不同。这些发现为IVR研究提供了重要的参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental study on the heat transfer characteristics of debris bed remelting process
The researches of IVR (In-Vessel Retention) primarily focuse on natural convection in steady-state molten pools. However, the dynamic process from particulate debris bed melting to molten pool is also critical. The debris beds remelting process may exhibit intermediate states that potentially exceed steady-state thermal loads, while simultaneously serving as the initial condition for steady-state molten pools. This study conducted experimental investigations on single-component and two-component debris bed remelting processes using the COREM-HT experimental facility. The results included phenomenological characteristics, temperature evolution and heat flux distribution. In both experiments, no transient heat flux exceeding the final state was observed. Notably, two crust layer observed on the wall differed from conventional steady-state molten pool configurations with single oxide crust. These findings offer significant references for IVR research.
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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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