Thermal creep in a pre-hydrided Zr1 % Nb nuclear fuel cladding tube-Reference-Cited by-同舟云学术

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Thermal creep in a pre-hydrided Zr1 % Nb nuclear fuel cladding tube

Published:2024-08 Issue: Volume:596 Page:155084
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Sklenicka Vaclav^ORCID,Kucharova Kveta,Kral Petr^ORCID,Dvorak Jiri^ORCID,Kvapilova Marie,Vrtilkova Vera,Krejci Jakub

Funder

Technology Agency of the Czech Republic

Publisher

Elsevier BV

Reference79 articles.

1. Development of zirconium-barrier fuel cladding;Amijo,1994

2. Properties of zirconium alloys and their applications in light water reactors (LWRs) components;Adamson,2013

3. Creep deformation of materials in light water reactors (LWRs);Murty,2013

4. Zirconium alloys for LWR fuel cladding and core intervals;Yagnik,2019

5. Radiation and thermomechanical degradation effects in reactor structural alloys;Zinkle,2019

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1. Creep Performance of Iron Tailing Sand Foam Concrete;2024

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