Preparation of the highly dense ceramic-metal fuel particle with fine-grained tungsten layer by chemical vapor deposition for the application in nuclear thermal propulsion

被引:14
作者
Guo, Li-Hua [1 ,2 ]
Zhang, Feng [1 ,3 ]
Lu, Lin-Yuan [1 ,2 ]
You, Yan [4 ]
Lu, Jun-Qiang [4 ]
Zhu, Li-Bing [4 ]
Lin, Jun [1 ,3 ]
机构
[1] Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
[2] Univ Chinese Acad Sci, Beijing 100049, Peoples R China
[3] Wuwei Inst New Energy, Wuwei 733000, Peoples R China
[4] Shanghai Nucl Engn Res & Design Inst Co Ltd, Shanghai 200233, Peoples R China
基金
上海市自然科学基金;
关键词
Deposition temperature; Tungsten layer; Ceramic-metal fuel particle; Nuclear thermal propulsion; Chemical vapor deposition; MECHANICAL-PROPERTIES; W/UO2;
D O I
10.1007/s42864-021-00117-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The cermet fuel element was achieved by dispersing the UO2 particles with or without tungsten (W) coating layer uniformly in the W matrix. It is considered to be a robust and secure fuel for use in nuclear thermal propulsion in the near future. In this study, the effect of deposition temperature on the densification and grain refinement of the W coating layer was investigated. A high-density (19.24 g.cm(-3)) W layer with a uniform thickness (similar to 10 mu m) and fine grains (similar to 297 nm) was prepared by spouted-bed chemical vapor deposition. The prepared high-density, fine-grained W layer has the following advantages. It can prevent direct contact between fuel particles, resulting in a more uniform fuel distribution. In addition, it can decrease the reaction probability between the fuel kernel and H-2, and prevent the release of fission products from the fuel kernel by extending the diffusion path at grain boundaries more efficiently. Moreover, the high-density, fine-grained W layer showed outstanding thermal and mechanical performance. Its average hardness and Young's modulus were approximately 7 and 200 GPa, respectively. The thermal conductivity of the W film was 101-124 W.m(-1).K-1 at 298-773 K. This work furthers our understanding of the potential application of the high-density, fine-grained W layer in nuclear thermal propulsion.
引用
收藏
页码:1 / 9
页数:9
相关论文
共 33 条
[1]  
Barnes M.W., 2017, An Overview of CERMET Fuel Development at
[2]  
Bhattacharyya S.K., 2001, An Assessment of Fuels for Nuclear Thermal Propulsion
[3]  
Borowski Stanley K., 2013, AIAA SPACE 2013 C EX
[4]  
Brengle R., 1993, 29 JOINT PROP C EXH, P2111
[5]  
Broadway J, 2012, MANUFACTURE W UO 2 F
[6]  
Cowan C., 1987, ASME M
[7]  
Czysz P., 2009, FUTURE SPACECRAFT PR, V2, P574, DOI [10.1007/978-3-540-88814-7, DOI 10.1007/978-3-540-88814-7]
[8]   Review of Nuclear Thermal Propulsion Systems [J].
Gabrielli, Roland Antonius ;
Herdrich, Georg .
PROGRESS IN AEROSPACE SCIENCES, 2015, 79 :92-113
[9]   Literature review of thermal and radiation performance parameters for high-temperature, uranium dioxide fueled cermet materials [J].
Haertling, C. ;
Hanrahan, R. J., Jr. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 366 (03) :317-335
[10]  
Hickman R., 2012, Fabrication and Testing of CERMET Fuel Materials for Nuclear Thermal Propulsion