In Situ Investigations of the Hydrogen Uptake of Zirconium Alloys during Steam Oxidation-Reference-Cited by-同舟云学术

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In Situ Investigations of the Hydrogen Uptake of Zirconium Alloys during Steam Oxidation

Published:2018-01-01 Issue: Volume: Page:1114-1135
ISSN:
Container-title:Zirconium in the Nuclear Industry: 18th International Symposium
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Author:

Grosse Mirco¹,Steinbrueck Martin¹,Schillinger Burkhard²,Kaestner Anders³

Affiliation:

1. Karlsruhe Institute of Technology, Institute for Applied Materials, P.O. Box 3640, D-76021 Karlsruhe, DE

2. Technische Universität München, FRM II and Physik-Department E21, James-Franck-Str. 1, D-85748 Garching, DE

3. Neutron Imaging and Activation Group, Paul Scherrer Institut, CH-5232, Villigen, CH

Publisher

ASTM International

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Oxidation behavior of Zr-2.5Nb alloy exposed to steam in the temperature range of 600–1200 °C;Journal of Nuclear Materials;2024-04

2. Axial Variations of Oxide Layer Growth and Hydrogen Uptake of BWR Fuel Claddings under Steam Starvation Conditions;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01

3. Investigation of the oxidation behavior of Zircaloy-4 cladding in a mixture of air and steam;Journal of Nuclear Materials;2023-03

4. Investigation of breakaway corrosion observed during oxide growth in pure and low alloying element content Zr exposed in water at 360°C;Journal of Nuclear Materials;2022-01

5. In Situ Neutron Radiography Investigations of Hydrogen Related Processes in Zirconium Alloys;Applied Sciences;2021-06-22

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