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Adaptation of the point defect model to simulate oxidation kinetics of 316L stainless steel in the pressurised water reactor environment

Autor: J.E. Westraadt, T. Couvant, R.D. Knutsen, R.P. Matthews

Publikováno v: Corrosion Science. 185:109454

The kinetics of oxide growth on 316 L stainless steel was measured after exposing samples, to a typical primary water environment at three temperatures (290℃, 320℃ and 360℃) and for test durations ranging from 1 h to 7000 h. Contrary to expecte

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::96cba0e3cb93c5a71bdda595898ab425
https://doi.org/10.1016/j.corsci.2021.109454

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Energy ordering of grain boundaries in Cr2O3: Insights from theory

Autor: Mazharul M. Islam, Boubakar Diawara, T. Couvant, A.G. Van Der Geest

The grain boundaries (GBs) of corundum Cr2O3 are known to play an important role in the diffusion of ions within the oxide, which is an important phenomenon for the corrosion of stainless steels. The extent of the growth of oxide layers in stainless

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::56cddfa0470e453c8d677a9c34d49601

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Corrosion in pressurized water reactors (PWRs)

Autor: T. Couvant

Corrosion is one of the major obstacles to extending the lifetime of nuclear power plants within agreed safety requirements. A large variety of the structural metals present in primary and secondary circuits of pressurized water reactors (PWRs) suffe

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9600416b0ca620f551ade26413735c05
https://doi.org/10.1533/9780857097453.1.70

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PWSCC of Thermocoax Pressurizer Heaters in Austenitic Stainless Steel and Remedial Actions to Preventing SCC

Autor: K. Dubourgnoux, D. Lecharpentier, Y. Neau, P. Moulart, A. Breuil, J. Champredonde, V. Derouet, T. Couvant, J.-M. Fageon, Y. Thebault

Publikováno v: Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors ISBN: 9783319487601
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Few cases of SCC have been observed in French PWRs, in high strain hardened and non-sensitized austenitic stainless steels exposed to nominal primary environment. In particular, Intergranular SCC has been observed on several pressurizer heaters. Thus

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::10749738eecd3044c167bcd0c4b4816d
https://doi.org/10.1002/9781118456835.ch230

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Effect of cold work hardening on stress corrosion cracking of stainless steels in primary water of pressurized water reactors

Autor: O. Raquet, E. Herms, T. Couvant, Jean-Marie Boursier, F. Vaillant

Publikováno v: Corrosion Issues in Light Water Reactors ISBN: 9781420060010

A R and D program is carried out in CEA and EDF laboratories to investigate separately the effects of factors which could contribute to IASCC mechanism. In the framework of this study, the influence of cold work on SCC of ASSs in primary water is stu

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::10d0b7540f973a8a0cfef6387de03eaf
https://doi.org/10.1533/9781845693466.2.76

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