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Effect of dissolved hydrogen on the crack growth rate and oxide film formation at the crack tip of alloy 600 exposed to simulated pwr primary water
Studsvik Nuclear AB, Sweden.
Studsvik Nuclear AB, Sweden.
RISE - Research Institutes of Sweden, Swerea, Swerea KIMAB.
Swedish Radiation Safety Authority, Sweden.
Show others and affiliations
2018 (English)In: Part of the The Minerals, Metals & Materials Series book series (MMMS), 2018, p. 423-437Conference paper, Published paper (Refereed)
Abstract [en]

The effect of dissolved hydrogen (DH) on primary water stress corrosion cracking of nickel base alloys has been of intense interest for plant operators worldwide. In this study, crack growth rates of Alloy 600 were measured in simulated PWR primary coolant at 330, °C with DH levels of 5, 16, 45 and 75, cc, H2/kg H2O, respectively. The oxide films formed in the crack tip regions were examined using transmission electron microscopy (TEM). The results show low and similar crack growth rates at all DH levels, without a maximum at 16, cc, H2/kg H2O. The low DH content favors nickel oxide formation at the crack tip region, whereas the high DH level favors Me3O4 type spinel formation. Also, the oxide films were found to grow epitaxially on some metal grain surfaces in the cracks. The possible effects of alloy composition on the oxide films formed, and the effect of DH on the crack growth are briefly discussed.

Place, publisher, year, edition, pages
2018. p. 423-437
Keywords [en]
Alloy 600, Dissolved hydrogen, High resolution microscopy, Oxide characterization, PWSCC, Characterization, Crack propagation, Crack tips, Cracks, Dissolution, Film growth, Growth rate, High resolution transmission electron microscopy, Nickel, Nickel alloys, Nickel oxide, Nuclear energy, Nuclear fuels, Pressurized water reactors, Stress corrosion cracking, Transmission electron microscopy, High-resolution microscopy, Nickel base alloys, Primary water stress corrosion cracking, PWR primary coolants, PWR primary waters, Oxide films
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Natural Sciences
Identifiers
URN: urn:nbn:se:ri:diva-33410DOI: 10.1007/978-3-319-67244-1_27Scopus ID: 2-s2.0-85042516409ISBN: 9783319672434 OAI: oai:DiVA.org:ri-33410DiVA, id: diva2:1188779
Conference
Environmental Degradation of Materials in Nuclear Power Systems EDM 2017: Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. 13 August 2017 through 17 August 2017
Note

Funding details: FSAI, Food Safety Authority of Ireland; Funding details: KTH, Kungliga Tekniska Högskolan; Funding details: TEM, Työ- ja Elinkeinoministeriö; 

Available from: 2018-03-08 Created: 2018-03-08 Last updated: 2018-03-16Bibliographically approved

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