中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Heat transfer characteristic analysis of a novel annular nuclear heat exchanger for propulsion system

文献类型:期刊论文

作者Bai, Ying1,2; Zhao, Zhumin1; Xu, Gang1; Bai, Yunqing1
刊名ANNALS OF NUCLEAR ENERGY
出版日期2019-04-01
卷号126期号:页码:84-94
关键词Annular channel Nuclear thermal propulsion Enhanced convection heat transfer Performance optimization
ISSN号0306-4549
DOI10.1016/j.anucene.2018.10.051
英文摘要

In conventional nuclear propulsion systems, reactor with gas-cooled core is bulky and requires extra space to be placed. A new type of nuclear heat exchanger with multi-annular structure is directly put into the combustion chamber to heat compressed air. Nuclear fuel is evenly embedded into the annular wall, which guarantees a steady energy supply to meet the propulsion needs. Because of the strong heat transfer capacity, the reactor is smaller, more compact and flexible. In this paper, a numerical model of propulsion and heat transfer is established for the nuclear jet engine to verify the feasibility of the novel nuclear heat exchanger. To find the optimal structure for cruise and after-burning flight, flow and heat transfer characteristics of the new reactor system are studied by adjusting the annulus numbers in the finite space. The sensitivity of the external control variables to the improvement of propulsion performance is investigated under the new structure. Finally, reactor performance is analyzed by physical-thermal coupling calculation in core. The analysis results show that the multi-annular nuclear heat exchanger has the optimal structure at the intersection point of characteristic parameter normalization. The multi-annular structure with n = 64 has more uniform power distribution, which is selected as the optimal structure for the new system. It can meet the heat transfer and thrust requirements from cruise to after-burning flight. The new system reduces the additional reactor configuration and saves the afterburner space, which is of great importance to the miniaturization and performance improvement of the nuclear propulsion system. (C) 2018 Elsevier Ltd. All rights reserved.

WOS关键词TURBULENT UPFLOW ; CHANNEL
资助项目Natural Science Foundation of Anhui Province of China[1608085ME107] ; National science and technology support project[2015 BAA08B01]
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000458944500009
出版者PERGAMON-ELSEVIER SCIENCE LTD
资助机构Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; Natural Science Foundation of Anhui Province of China ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project ; National science and technology support project
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/42126]  
专题合肥物质科学研究院_中国科学院核能安全技术研究所
通讯作者Zhao, Zhumin
作者单位1.Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China
2.Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China
推荐引用方式
GB/T 7714
Bai, Ying,Zhao, Zhumin,Xu, Gang,et al. Heat transfer characteristic analysis of a novel annular nuclear heat exchanger for propulsion system[J]. ANNALS OF NUCLEAR ENERGY,2019,126(无):84-94.
APA Bai, Ying,Zhao, Zhumin,Xu, Gang,&Bai, Yunqing.(2019).Heat transfer characteristic analysis of a novel annular nuclear heat exchanger for propulsion system.ANNALS OF NUCLEAR ENERGY,126(无),84-94.
MLA Bai, Ying,et al."Heat transfer characteristic analysis of a novel annular nuclear heat exchanger for propulsion system".ANNALS OF NUCLEAR ENERGY 126.无(2019):84-94.

入库方式: OAI收割

来源:合肥物质科学研究院

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