轴向闭式布雷顿循环压缩机在氦-氮混合气体中运行的性能特征

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Arif Aziz , Qun Zheng , Adil Malik , Ghulam Ishaque , Muhammad Haris , Phengphanh Taikeophithoun
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引用次数: 0

摘要

本研究评估了氦氮混合物作为地面核设施轴向压缩机工作介质的可能性。纯净的氦由于其优越的传输能力而被认为是一种极好的冷却剂,然而它在压缩方面提出了挑战。因此,高温气冷堆(HTGR)能源系统会导致涡轮机械的尺寸增加、质量增加、成本增加和动态问题。本文对氦氮二元气体混合物在一定条件下的热物理性质和输运性质进行了详细的研究,结果表明,当其摩尔质量为13 g/mol时,传热系数提高了4.2%。为此,设计了一种新型氦氮压缩机。进行了性能评价,结果表明,要达到氦氮压缩机所要求的压力,氦气压缩机只需要22.86%的级。在封闭Brayton循环(CBC)上运行的HTGR已将其压缩机级从16级减少到4级。因此,氦-氮二元气体混合物比纯氦更适合用于高温气冷堆电厂的涡轮压气机。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Performance characterization of an axial closed Brayton cycle compressor operating with helium-nitrogen gas mixture
This study evaluates the possible use of a mixture of helium-nitrogen as a working medium in axial compressors employed in terrestrial nuclear facilities. As helium in its pure form is considered to be an excellent coolant owing to its superior transport capabilities, nonetheless it poses challenges in compression. With this, the high temperature gas cooled reactor (HTGR) energy systems result in increased size, greater mass, elevated costs, and dynamic issues in turbomachinery. This research provides the detailed investigation of thermophysical and transport properties of helium and nitrogen binary gas mixture at specified conditions which demonstrate that the heat transfer coefficient enhances by 4.2 % when its molar weight equals 13 g/mole. Therefore, a new helium-nitrogen compressor is subsequently designed. The performance evaluation is done, and the results indicate that just 22.86 % of the stages in the helium compressor are necessary to attain the requisite pressure in a helium-nitrogen compressor. The HTGR operating on the closed Brayton cycle (CBC) has decreased its compressor stages from 16 to 4 only. As a result, helium-nitrogen binary gas mixture is more appropriate for use in the turbocompressors of HTGR power plants than pure helium.
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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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