Oxidation behavior of Zr-2.5Nb alloy exposed to steam in the temperature range of 600

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Oxidation behavior of Zr-2.5Nb alloy exposed to steam in the temperature range of 600–1200 °C

Published:2024-04 Issue: Volume:592 Page:154967
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Krishna V.S.V. Anantha,Nouduru Sai Karthik,Mandapaka Kiran K.,Ahmedabadi Parag M.,Abraham Geogy J.,Shukla S.,Roychowdhury S.,Kain V.^ORCID

Publisher

Elsevier BV

Reference69 articles.

1. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys;Cox;J. Nucl. Mater.,2005

2. Advances in zirconium technology for nuclear reactor application;Ganguly,2002

3. Applications related metallurgy of zirconium, niobium and beryllium;Sundaram;Trans. Indian Inst. Met.,1986

4. IAEA Status report 74 - Indian 220 MWe PHWR (IPHWR-220) Tech,2011

5. IAEA Status report 105 - Indian 700 MWe PHWR (IPHWR-700) Tech,2011

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