Comments to papers of J.H. Kim et al. [1] and M. Große et al. [2] recently published in JNM “On the hydrogen uptake of Zircaloy-4 and M5™ alloys subjected to steam oxidation in the 1100–1250°C temperature range”-Reference-Cited by-同舟云学术

Comments to papers of J.H. Kim et al. [1] and M. Große et al. [2] recently published in JNM “On the hydrogen uptake of Zircaloy-4 and M5™ alloys subjected to steam oxidation in the 1100–1250°C temperature range”

Published:2009-12 Issue:1-3 Volume:395 Page:169-172
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Brachet J.-C.,Vandenberghe V.

Publisher

Elsevier BV

Subject

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

Reference18 articles.

1. Failure behavior of Zircaloy-4 cladding after oxidation and water quench

2. Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation

3. L. Yegorova, K. Lioutov, N. Jouravkova, A. Konobeev, V. Smirnov, V. Chesanov, A. Goryachev, Experimental Study of Embrittlement of Zr–1%Nb VVER Cladding under LOCA-Relevant Conditions, NUREG/IA-0211/IRSN 2005-194/NSI RRC KI 3188 Report, 2005.

4. M. Billone, Y. Yan, T. Burtseva, Cladding Embrittlement during Postulated Loss-of-Coolant Accidents, ANL NUREG/CR-6967 Report, ML082130389, 2008-07-31.

5. Ductile-to-brittle transition of oxidised Zircaloy-4 and E110 claddings

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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. Study of oxidation behavior and associated microstructure evolution of Zircaloy-4 exposed to high temperature pure steam;Vacuum;2023-05

3. Steam oxidation behavior of ZrO2/Cr-coated pure zirconium prepared by plasma electrolytic oxidation followed by filtered cathodic vacuum arc deposition;Journal of Alloys and Compounds;2021-11

4. Effect of pre-oxide on Zircaloy-4 high temperature steam oxidation;Journal of Nuclear Materials;2021-05

5. Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C;Corrosion Science;2020-11