Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C

Author:

Ding Guochen,Zhang Jing,Wang Jie,Li Yong,Jian Xiaobin,Ding Shurong,Deng Yongjun

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference61 articles.

1. Shurong Ding. Multi-physics modeling of delayed hydride cracking in zirconium alloys;Xia;J. Mech. Phys. Solids,2019

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3. Structurally induced enhancement in corrosion resistance of Zr–2.5%Nb alloy in saline solution by applying ultrasonic impact peening;Mordyuk;Mater. Sci. Eng. A,2013

4. Nuclear fuels – Present and future;Olander;J. Nucl. Mater.,2009

5. Shurong Ding. A theoretical model for delayed hydride cracking velocity considering the temperature history and temperature gradients;Zhang;Nucl. Mater. Energy,2018

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