PWR Zircaloy cladding corrosion behavior: quantitative analyses-Reference-Cited by-同舟云学术

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PWR Zircaloy cladding corrosion behavior: quantitative analyses

Published:1997-09 Issue: Volume:248 Page:281-287
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kido T.,Kanasugi K.,Sugano M.,Komatsu K.

Publisher

Elsevier BV

Subject

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

Reference31 articles.

1. Proc. ANS Int. Topical Meeting on Light Water Reactor Fuel Performance;Limback,1994

2. Proc. EPRI, Utility Workshop on PWR Fuel Corrosion;Sabol,1993

3. 11th Int. Symp. on Zirconium in the Nuclear Industry;Besch,1995

4. Enlarged Halden Programme Group Meeting;Hayashi,1996

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1. Peculiarities of interaction between oxygen and solute/vacancy in commercial-type zirconium-based alloys: A first-principles study;Materials Today Communications;2024-03

2. Peculiarities of Interaction between Oxygen and Solute/Vacancy in Commercial-Type Zirconium-Based Alloys: A First-Principles Study;2023

3. The accommodation of lithium in bulk ZrO2;Solid State Ionics;2021-12

4. Pt catalytic effects on the corrosion and hydrogen chemisorption properties of Zircaloy-2;Journal of Nuclear Materials;2021-02

5. Effect of neutron and ion irradiation on the metal matrix and oxide corrosion layer on Zr-1.0Nb cladding alloys;Acta Materialia;2019-07

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