THE EFFECTS OF CREEP AND HYDRIDE ON SPENT FUEL INTEGRITY DURING INTERIM DRY STORAGE
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference5 articles.
1. LWR Spent Fuel Storage Behaviour
2. Rupture of spent fuel Zircaloy cladding in dry storage due to delayed hydride cracking
3. Transitions in creep mechanisms and creep anisotropy in Zr1Nb1Sn0.2Fe sheet
4. Evaluation of the thermal creep behaviors and microstructure of Zircaloy-4 strip
5. Effect of radial hydrides on the axial and hoop mechanical properties of Zircaloy-4 cladding
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1. Recrystallization and grain growth of Zr-Nb-Sn alloy in 400–500 °C and effect on hydride embrittlement;Journal of Nuclear Materials;2023-09
2. Modeling hydride growth and strain-field evolution at a stress concentrator in zirconium alloys;Computational Materials Science;2023-02
3. Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling;Journal of Nuclear Materials;2021-11
4. Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials;Coatings;2020-08-21
5. Study hydrogen embrittlement and determination of E110 fuel cladding mechanical properties by ring compression testing;IOP Conference Series: Materials Science and Engineering;2018-12-10
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