Radial Delayed Hydride Cracking in Irradiated Zircaloy-2 Cladding: Advanced Characterization Techniques-Reference-Cited by-同舟云学术

Radial Delayed Hydride Cracking in Irradiated Zircaloy-2 Cladding: Advanced Characterization Techniques

Published:2023-11-01 Issue: Volume: Page:260-285
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Container-title:Zirconium in the Nuclear Industry: 20th International Symposium
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Author:

Colldeweih Aaron W.¹^ORCID,Fagnoni Francesco¹^ORCID,Yetik Okan¹²^ORCID,Zubler Robert¹,Trtik Pavel²^ORCID,Anghel Clara³^ORCID,Pouchon Manuel A.¹^ORCID,Dai Yong¹,Duarte Liliana I.¹^ORCID,Bertsch Johannes¹^ORCID

Affiliation:

1. Laboratory for Nuclear Materials, Paul Scherrer Institute, Villigen, Aargau, 5200, CH

2. Laboratory for Neutron Scattering, Paul Scherrer Institute, Villigen, Aargau, 5200, CH

3. Sweden Fuel Engineering, Westinghouse Electric Sweden, Västerås, 721 63, SE

Publisher

ASTM International

Reference49 articles.

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2. Hydrogen Diffusion and Precipitation in Duplex Zirconium Nuclear Fuel Cladding Quantified by High-Resolution Neutron Imaging;Gong;Journal of Nuclear Materials,2019

3. Hydride Reorientation and Delayed Hydride Cracking of Spent Fuel Rods in Dry Storage;Kim;Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science,2008

4. Hydrogen in Zircaloy: Mechanism and Its Impacts;Suman;International Journal of Hydrogen Energy,2015

5. M. P. Puls, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking (New York, NY: Springer, 2012).