利用 SST k-ω-kθ-εθ 模型对钠冷快堆环形燃料组件的湍流传热进行数值研究

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Journal of Nuclear Science and Technology Pub Date : 2024-02-05 DOI:10.1080/00223131.2024.2310563

Yuefeng Guo, Xingkang Su, Guan Wang, Xianwen Li, Long Gu

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引用次数: 0

摘要

环形燃料有内外两个冷却面，可以充分带走燃料组件的热量，具有很强的安全性和经济性。目前，迫切需要对环形燃料进行重新设计。

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 Study of Turbulent Heat Transfer of Annular Fuel Assembly in a Sodium-cooled Fast Reactor by a SST k-ω-kθ-εθ Model

The annular fuel has two cooling surfaces inside and outside, which can fully take away the heat of the fuel assemblies, and have strong advantages in safety and economy. It is urgent to conduct re...

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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.