Zhenhong Wang
China Academy of Engineering Physics
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Publication
Featured researches published by Zhenhong Wang.
Journal of Nuclear Materials | 2002
Maobing Shuai; Yong-Jun Su; Zhenhong Wang; Pengji Zhao; Juesheng Zou; Sheng Wu
Hydrogen absorption–desorption properties of the UZr0.29 alloy and uranium metal were investigated in detail at hydrogen pressures as high as to 0.4 MPa and over the temperature range of 300–723 K. Both UZr0.29 alloy and uranium metal showed similar hydrogen isotopic effect and hysteresis effect. UZr0.29 alloy absorbed hydrogen (deuterium) up to 2.3H (2.18D) atoms per F.U. (formula unit) by only one-step reaction and hence each desorption isotherm had a single plateau over nearly the whole hydrogen composition range. The UZr0.29 alloy showed a little lower dissociation pressure than that of pure uranium; however, it exhibited high durability against powdering upon hydrogenation and may have good heat conductivity. The UZr0.29 hydride has the potentiality to substitute pure uranium hydride as a material for tritium treatment and storage.
Materials Science and Technology | 2018
Dong Chen; Xianglin Chen; Rong Ma; Qingfu Tang; Bin Su; Zhenhong Wang; Xinjian Zhang; Daqiao Meng
ABSTRACT The microstructure and tensile properties of an aged U-5.5u2009wt-% Nb alloy have been experimentally investigated with the aim of obtaining the influence of strain rates on fracture behaviour. The result shows that strain to failure is sensitive to strain rate and decreases with an increase in the strain rate. Fracture surface analysis indicates that the alloy exhibits a typical ductile fracture. Two types of carbides (niobium carbide and uranium carbide), mainly distributed at the grain boundary, are confirmed, which participate in the process of fracture and are involved in different void nucleation mechanisms during the final ductility fracture. Namely, niobium carbide tends to generate voids by debonding with the matrix, while uranium carbide is more likely to experience cracking.
Chinese Materials Conference | 2017
Yanhui Bai; Bin Su; Qingfu Tang; Qingfu Wang; Wenpeng Li; Zhenhong Wang
Uranium and uranium alloys are a kind of important nuclear materials with unique physics and chemical properties. Unfortunately, it is eroded easily, especially in humid environment. In this paper, Ni coating and Ni+Zn composite coating were prepared on the surface of U–Ti alloy. The adhesion strength, phase structure and corrosion properties were characterized by tensile method, X-ray diffraction and electrochemical methods. The results showed that the Ni coating was a face centered cubic structure, while the anodic Ni+Zn composite coating was hexagonal structure. The average adhesion strength of composite coating was 16.0 MPa. The corrosion protection of composite coating was mainly due to the electrochemical protection of Zn coating and the physic barrier function of Ni coating.
Journal of Alloys and Compounds | 2016
Fengsheng Qu; Z.Y. Reng; Rong Ma; Zhenhong Wang; Dong Chen
Journal of Nuclear Materials | 2017
Zhiyong Ren; Rong Ma; Guichao Hu; Jun Wu; Zhenhong Wang; Chao Luo
Revue De Metallurgie-cahiers D Informations Techniques | 2018
Dong Chen; Rong Ma; Xianglin Chen; Zhenhong Wang; Bin Su; Xinjian Zhang; Daqiao Meng
Materials Research Express | 2017
Dong Chen; Ruiwen Li; Dingmu Lang; Zhenhong Wang; Bin Su; Xinjian Zhang; Daqiao Meng
Journal of Nuclear Materials | 2017
Zhiyong Ren; Guichao Hu; Rong Ma; Jun Wu; Zhenhong Wang; Chao Luo
Materials Science and Engineering A-structural Materials Properties Microstructure and Processing | 2019
Dong Chen; Xinjian Zhang; Haoxi Wu; Dingmu Lang; Dawu Xiao; Zhenhong Wang; Bin Su; Daqiao Meng
Materials Science and Engineering A-structural Materials Properties Microstructure and Processing | 2018
Dong Chen; Xinjian Zhang; Xiandong Meng; Rong Ma; Ruiwen Li; Zhenhong Wang; Bin Su; Dingmu Lang; Tian Yang; Daqiao Meng