Influence of the transient conditions on release of corrosion products and oxidation of alloy 690 tubes during pressurized water reactor restart after steam generators replacement-Reference-Cited by-同舟云学术

Influence of the transient conditions on release of corrosion products and oxidation of alloy 690 tubes during pressurized water reactor restart after steam generators replacement

Published:2021-01 Issue: Volume:543 Page:152562
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Flambard Julie,Carrette Florence^ORCID,Monchy-Leroy Carole,Andrieu Eric,Laffont Lydia

Publisher

Elsevier BV

Subject

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

Reference27 articles.

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3. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor;Sennour;Journal of Nuclear Materials,2010

4. Analysis and TEM examinations of corrosion scales grown on Alloy 690 exposed to pressurized water at 325°C: Corrosion scales on Alloy 690 grown in pressurized water;Carrette;Surface and Interface Analysis,2002

5. Analysis and TEM examinations of corrosion scales grown on alloy 690 exposed to PWR environment;Carrette;Materials at High Temperatures,2003

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