Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments-Reference-Cited by-同舟云学术

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Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments

Published:1968-10 Issue:1 Volume:28 Page:1-47
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Cox B.

Publisher

Elsevier BV

Subject

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

Reference163 articles.

1. IAEA Symp. Fuel Element Fabrication (with special emphasis on cladding materials);Thomas,1960

2. Homogeneous Reactor Project;Jenks;Quarterly Progress Reports, U.S.A. Reports, ORNL No. 1813, 1943, 2004, 2057, 2096, 2148, 2222, 2272, 2331, 2379, 2432,1954

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1. Interface Stability of Ultrasonic Additively Manufactured Zircaloy-4 during Hydrothermal Corrosion;Journal of Nuclear Materials;2024-09

2. Dynamic Charge Carrier Transport Behaviors in Zirconium Oxide for Nuclear Cladding Materials;Archives of Metallurgy and Materials;2023-07-26

3. Effects of Radiation-Induced Defects on Corrosion;Annual Review of Materials Research;2021-07-26

4. Comprehensive modeling of hydrogen transport and accumulation in titanium and zirconium;Nuclear Materials and Energy;2020-05

5. Effect of dissolved oxygen on corrosion behavior of Zr–0.85Sn–0.16Nb–0.37Fe–0.18Cr alloy in 500 °C and 10.3 MPa super-heated steam;Transactions of Nonferrous Metals Society of China;2020-03

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