浮动核电平台燃料组件流动与传热数值模拟

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Science and Technology Pub Date : 2023-12-04 DOI:10.1080/00223131.2023.2290712

Guopeng Liang, Yunlong Wang, Guan Guan, Chaoguang Jin, Ming Chen

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引用次数: 0

摘要

浮动核电平台(FNPP)与陆上核电站不同，它在海上承受周期性的滚动载荷。这些载荷将对流动特性产生更明显的影响。

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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Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform

Floating nuclear power platform (FNPP), unlike onshore nuclear power plants, is subjected to periodic rolling loads at sea. These loads will have a more obvious impact on the flow characteristics a...

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来源期刊

Journal of Nuclear Science and Technology 工程技术-核科学技术

CiteScore

2.40

自引率

16.70%

发文量

116

审稿时长

2.3 months

期刊介绍： The Journal of Nuclear Science and Technology (JNST) publishes internationally peer-reviewed papers that contribute to the exchange of research, ideas and developments in the field of nuclear science and technology, to contribute peaceful and sustainable development of the World. JNST ’s broad scope covers a wide range of topics within its subject category, including but are not limited to: General Issues related to Nuclear Power Utilization: Philosophy and Ethics, Justice and Policy, International Relation, Economical and Sociological Aspects, Environmental Aspects, Education, Documentation and Database, Nuclear Non-Proliferation, Safeguard Radiation, Accelerator and Beam Technologies: Nuclear Physics, Nuclear Reaction for Engineering, Nuclear Data Measurement and Evaluation, Integral Verification/Validation and Benchmark on Nuclear Data, Radiation Behaviors and Shielding, Radiation Physics, Radiation Detection and Measurement, Accelerator and Beam Technology, Synchrotron Radiation, Medical Reactor and Accelerator, Neutron Source, Neutron Technology Nuclear Reactor Physics: Reactor Physics Experiments, Reactor Neutronics Design and Evaluation, Reactor Analysis, Neutron Transport Calculation, Reactor Dynamics Experiment, Nuclear Criticality Safety, Fuel Burnup and Nuclear Transmutation, Reactor Instrumentation and Control, Human-Machine System: Reactor Instrumentation and Control System, Human Factor, Control Room and Operator Interface Design, Remote Control, Robotics, Image Processing Thermal Hydraulics: Thermal Hydraulic Experiment and Analysis, Thermal Hydraulic Design, Thermal Hydraulics of Single/Two/Multi Phase Flow, Interactive Phenomena with Fluid, Measurement Technology...etc.