In-reactor oxidation of crevices and cracks in cold-worked Zr-2.5 wt% Nb-Reference-Cited by-同舟云学术

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In-reactor oxidation of crevices and cracks in cold-worked Zr-2.5 wt% Nb

Published:1977-12 Issue:1 Volume:71 Page:25-35
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Causey A.R.,Urbanic V.F.,Coleman C.E.

Publisher

Elsevier BV

Subject

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

Reference11 articles.

1. Susceptibility of zirconium alloys to delayed hydrogen cracking;Coleman,1976

2. On the factors controlling hydrogen assisted sub-critical crack growth in Zr-2.5 wt% Nb;Simpson,1976

3. Effect of Aging and Irradiation on the Corrosion of Zr-2.5 Wt% Nb

Cited by 12 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Thermodynamics and kinetics of delayed hydride cracking in zirconium alloys: A review;Journal of Nuclear Materials;2024-12

2. Gamma-zirconium hydride on DHC fracture surfaces is a legitimate stable phase, not a metastable phase;Journal of Nuclear Materials;2021-05

3. Diffusivity of hydrogen isotopes in the alpha phase of zirconium alloys interpreted with the Einstein flux equation;Journal of Nuclear Materials;2018-11

4. High temperature and high pressure oxidation behavior of Zr-2.5Nb pressure tube material – Effect of β phase composition and surface machining;Journal of Nuclear Materials;2016-03

5. Prospects of chemical vapor grown silicon carbide thin films using halogen-free single sources in nuclear reactor applications: A review;Journal of Materials Research;2012-07-31

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