Institutional Repository of Chinese Academy of Sciences, Institute of Nuclear Energy Safety Technology, Hefei, Anhui 230031, China
Heat transfer characteristic analysis of a novel annular nuclear heat exchanger for propulsion system | |
Bai, Ying1,2; Zhao, Zhumin1; Xu, Gang1; Bai, Yunqing1 | |
2019-04-01 | |
发表期刊 | ANNALS OF NUCLEAR ENERGY |
ISSN | 0306-4549 |
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. |
关键词 | Annular channel Nuclear thermal propulsion Enhanced convection heat transfer Performance optimization |
DOI | 10.1016/j.anucene.2018.10.051 |
关键词[WOS] | TURBULENT UPFLOW ; CHANNEL |
收录类别 | SCI |
语种 | 英语 |
资助项目 | Natural Science Foundation of Anhui Province of China[1608085ME107] ; National science and technology support project[2015 BAA08B01] |
项目资助者 | 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 |
WOS研究方向 | Nuclear Science & Technology |
WOS类目 | Nuclear Science & Technology |
WOS记录号 | WOS:000458944500009 |
出版者 | PERGAMON-ELSEVIER SCIENCE LTD |
引用统计 | |
文献类型 | 期刊论文 |
条目标识符 | http://ir.hfcas.ac.cn:8080/handle/334002/42126 |
专题 | 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 |
第一作者单位 | 中国科学院核能安全技术研究所 |
通讯作者单位 | 中国科学院核能安全技术研究所 |
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. |
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