Network


Latest external collaboration on country level. Dive into details by clicking on the dots.

Hotspot


Dive into the research topics where Zishou Zhao is active.

Publication


Featured researches published by Zishou Zhao.


Journal of Nuclear Science and Technology | 2015

Effects of alloying elements (Sn, Nb, Cr, and Mo) on the microstructure and mechanical properties of zirconium alloys

Huilong Yang; Jingjie Shen; Y. Matsukawa; Yuhki Satoh; Sho Kano; Zishou Zhao; Yanfen Li; Feng Li; Hiroaki Abe

The alloying effects of Sn, Nb, Cr, and Mo on zirconium alloys were elucidated and compared. Electron backscatter diffraction, transmission electron microscopy, tensile test, and fractographic observation were jointly utilized to carry out detailed microstructural characterization and mechanical property evaluation. Results show that Mo is the most effective among these elements from the viewpoints of strengthening and reducing grain size. The strengthening mechanism for each element is also discussed. The order of solid-solution strengthening of these alloying elements is Cr > Nb > Sn, and the sequence is Cr ≈ Mo > Nb when precipitation strengthening is considered. Further, as far as the ability to impede dislocation motion is concerned, the sequence is Mo > Cr > Nb > Sn. The experimental results demonstrate that minor amount of Mo addition in zirconium alloys is greatly effective in strengthening the alloy and reducing the grain size.


Journal of Nuclear Science and Technology | 2017

A comparative study of hydride-induced embrittlement of Zircaloy-4 fuel cladding tubes in the longitudinal and hoop directions

Zishou Zhao; Daichi Kunii; Tomonori Abe; Huilong Yang; Jingjie Shen; Yasunari Shinohara; Sho Kano; Y. Matsukawa; Yuhki Satoh; Hiroaki Abe

ABSTRACT In this work, the mechanical behavior of as-received and hydrogenated Zircaloy-4 fuel claddings was investigated by the newly developed advanced expansion due to compression (A-EDC) test and the conventional uniaxial tension (UT) test at room temperature, in order to, respectively, understand the hydride-induced embrittlement in tube longitudinal and hoop directions. The UT experimental results showed that the mechanical strength in the longitudinal direction slightly increased with hydrogen content, whereas the maximum strain decreased greatly with hydrogen increasing. In the case of A-EDC tests, the mechanical performance in the hoop direction seemed insensitive to the hydrogen content; no obvious decline in maximum strain was observed until 800 ppm H. The comparison between these two tests clearly reveals that the hydride-induced embrittlement is preferential to occur in the longitudinal direction, compared with the sluggish response in the hoop direction, which implied the enhanced ductility anisotropy due to hydrides. In the post-tests observation, the fracture morphologies became gradually distinct for the as-received and hydrided samples examined by UT and A-EDC methods, and different orientation relationships between the applied stresses and hydrides distribution would be responsible for that distinction.


Nuclear Engineering and Design | 2017

Current status of materials development of nuclear fuel cladding tubes for light water reactors

Zhengang Duan; Huilong Yang; Yuhki Satoh; Kenta Murakami; Sho Kano; Zishou Zhao; Jingjie Shen; Hiroaki Abe


Materials Science and Engineering A-structural Materials Properties Microstructure and Processing | 2016

Microstructural characterization and strengthening mechanisms of a 12Cr-ODS steel

Jingjie Shen; Yanfen Li; Feng Li; Huilong Yang; Zishou Zhao; Sho Kano; Y. Matsukawa; Yuhki Satoh; Hiroaki Abe


Materials Science and Engineering A-structural Materials Properties Microstructure and Processing | 2016

Study on recrystallization and correlated mechanical properties in Mo-modified Zr-Nb alloys

Huilong Yang; Sho Kano; Y. Matsukawa; Yongfeng Li; Jingjie Shen; Zishou Zhao; Feng Li; Yuhki Satoh; Hiroaki Abe


Acta Materialia | 2016

The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr

Y. Matsukawa; Huilong Yang; K. Saito; Yasukazu Murakami; T. Maruyama; T. Iwai; Kenta Murakami; Yasunari Shinohara; T. Kido; T. Toyama; Zishou Zhao; Yongfeng Li; Sho Kano; Yuhki Satoh; Yasuyoshi Nagai; Hiroaki Abe


Journal of Nuclear Materials | 2018

Investigation of instability of M 23 C 6 particles in F82H steel under electron and ion irradiation conditions

Sho Kano; Huilong Yang; Jingjie Shen; Zishou Zhao; John McGrady; Dai Hamaguchi; Mamami Ando; Hiroyasu Tanigawa; Hiroaki Abe


Materials Transactions | 2017

Mechanical Properties of Zircaloy-4 Cladding Tube by Advanced Expansion due to Compression (A-EDC) Test

Zishou Zhao; D. Kunii; Toshihiko Abe; Huilong Yang; Sho Kano; Y. Matsukawa; Yuhki Satoh; Hiroaki Abe


Journal of Nuclear Materials | 2017

Tensile properties and microstructure of Zr–1.8Nb alloy subjected to 140-MeV C4+ ion irradiation

Huilong Yang; Sho Kano; Yoshi Matsukawa; Jingjie Shen; Zishou Zhao; Zhengang Duan; Dongyue Chen; Kenta Murakami; Li Y; Yuhki Satoh; Hiroaki Abe


Nuclear materials and energy | 2018

Effects of pre-deformation on microstructural evolution of 12Cr ODS steel under 1473–1673 K annealing

Jingjie Shen; Huilong Yang; Zishou Zhao; John McGrady; Sho Kano; Hiroaki Abe

Collaboration


Dive into the Zishou Zhao's collaboration.

Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Researchain Logo
Decentralizing Knowledge