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Energy Materials
Materials Science and Engineering for Energy Systems
Volume 3, 2008 - Issue 2
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Articles

Contribution to understanding of stress corrosion cracking of Alloy 600 in PWR primary water

Pages 119-125 | Published online: 20 Nov 2013

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M. Wehbi, T. Couvant, C. Duhamel & J. Crepin. (2015) Oxidation of nickel-base welds 182 and 82 in simulated primary water of pressurised water reactors. Materials at High Temperatures 32:1-2, pages 1-9.
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Articles from other publishers (14)

L. Volpe, M.G. Burke & F. Scenini. (2020) Oxidation behaviour of solution-annealed and thermally-treated Alloy 690 in low pressure H2-Steam. Corrosion Science 167, pages 108514.
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S. Y. Persaud, B. Langelier, A. Eskandari, H. Zhu, G. A. Botton & R. C. Newman. 2019. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 375 398 .
S. Y. Persaud, B. Langelier, A. Eskandari, H. Zhu, G. A. Botton & R. C. Newman. 2018. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 375 398 .
William Gerberich, Ellad B. Tadmor, Jeffrey Kysar, Jonathan A. Zimmerman, Andrew M. Minor, Izabela Szlufarska, Jonathan Amodeo, Benoit Devincre, Eric Hintsala & Roberto Ballarini. (2017) Review Article: Case studies in future trends of computational and experimental nanomechanics. Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films 35:6.
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B. Langelier, S.Y. Persaud, A. Korinek, T. Casagrande, R.C. Newman & G.A. Botton. (2017) Effects of boundary migration and pinning particles on intergranular oxidation revealed by 2D and 3D analytical electron microscopy. Acta Materialia 131, pages 280-295.
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S.Y. Persaud & R.C. Newman. (2016) A Review of Oxidation Phenomena in Ni Alloys Exposed to Hydrogenated Steam Below 500°C. Corrosion 72:7, pages 881-896.
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S.Y. Persaud, J. Smith, A. Korinek, G.A. Botton & R.C. Newman. (2016) High resolution analysis of oxidation in Ni-Fe-Cr alloys after exposure to 315 °C deaerated water with added hydrogen. Corrosion Science 106, pages 236-248.
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Alisa Stratulat, David E.J. Armstrong & Steve G. Roberts. (2016) Micro-mechanical measurement of fracture behaviour of individual grain boundaries in Ni alloy 600 exposed to a pressurized water reactor environment. Corrosion Science 104, pages 9-16.
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D. F?ron, C. Guerre, E. Herms & P. Laghoutaris. 2016. Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors. Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors 325 353 .
S.Y. Persaud, S. Ramamurthy & R.C. Newman. (2015) The effect of weld chemistry on the oxidation of Alloy 82 dissimilar metal welds. Corrosion Science 91, pages 58-67.
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S.Y. Persaud, S. Ramamurthy & R.C. Newman. (2015) Internal oxidation of alloy 690 in hydrogenated steam. Corrosion Science 90, pages 606-613.
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S.Y. Persaud, A. Korinek, J. Huang, G.A. Botton & R.C. Newman. (2014) Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment. Corrosion Science 86, pages 108-122.
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C. Guerre, P. Laghoutaris, J. Chêne, L. Marchetti, R. Molins, C. Duhamel & M. Sennour. 2012. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 1477 1488 .
M. Sennour, P. Laghoutaris, C. Guerre & R. Molins. (2009) Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment. Journal of Nuclear Materials 393:2, pages 254-266.
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