Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking-Reference-Cited by-同舟云学术

Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking

Published:2023-03 Issue: Volume:27 Page:101689
ISSN:2589-1529
Container-title:Materialia
language:en
Short-container-title:Materialia

Author:

Colldeweih Aaron W.^ORCID,Makowska Malgorzata G.^ORCID,Tabai Omaïa,Sanchez Dario Ferreira,Bertsch Johannes

Funder

swissnuclear

Nationale Genossenschaft für die Lagerung radioaktiver Abfälle

Publisher

Elsevier BV

Subject

General Materials Science

Reference48 articles.

1. INTERNATIONAL ATOMIC ENERGY AGENCY, “Waterside corrosion of zirconium alloys in nuclear power plants,” IAEA-TECDOC-996, IAEA, Vienna (1998).

2. Effect of hydrogen injection on hydrogen uptake by BWR fuel cladding;Cox;Electr. Power Res. Inst.,1983

3. Embrittlement of reactor core materials;Kreyns,1996

4. Hydrogen pickup and redistribution in alpha-annealed Zircaloy-4;Kammenzind;ASTM Spec. Tech. Publ.,1996

5. The long-range migration of hydrogen through Zircaloy in response to tensile and compressive stress gradients;Kammenzind;ASTM Spec. Tech. Publ.,2000

Cited by 2 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. On the stable/metastable nature of the γ-hydride phase in Zircaloy-2: Microstructural characterization by electron diffraction, electron energy-loss spectroscopy, and diffraction line profile analysis;Journal of Nuclear Materials;2024-07

2. In-situ EBSD analysis of hydride phase transformation and its effect on micromechanical behavior in Zircaloy-4 under uniaxial tensile loading;Journal of Materials Research and Technology;2024-05