Arif Aziz , Qun Zheng , Adil Malik , Ghulam Ishaque , Muhammad Haris , Phengphanh Taikeophithoun
{"title":"Performance characterization of an axial closed Brayton cycle compressor operating with helium-nitrogen gas mixture","authors":"Arif Aziz , Qun Zheng , Adil Malik , Ghulam Ishaque , Muhammad Haris , Phengphanh Taikeophithoun","doi":"10.1016/j.nucengdes.2025.114496","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114496"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325006739","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
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.
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.