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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, Materials and Production, KIMAB.
Swedish Radiation Safety Authority, Sweden.
Show others and affiliations
2019 (English)In: Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Springer International Publishing , 2019, 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 H 2 /kg H 2 O, 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 H 2 /kg H 2 O. The low DH content favors nickel oxide formation at the crack tip region, whereas the high DH level favors Me 3 O 4 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
Springer International Publishing , 2019. p. 423-437
Keywords [en]
Alloy 600, Dissolved hydrogen, High resolution microscopy, Oxide characterization, PWSCC, Crack propagation, Dissolution, Film growth, Growth rate, High resolution transmission electron microscopy, Hydrogen, Nickel alloys, Nickel oxide, Nuclear fuels, Oxide films, 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, Crack tips
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Natural Sciences
Identifiers
URN: urn:nbn:se:ri:diva-38553DOI: 10.1007/978-3-030-04639-2_27Scopus ID: 2-s2.0-85064063084ISBN: 9783030046385 (print)ISBN: 9783030046392 (print)ISBN: 9783319515403 (print)ISBN: 9783319651354 (print)ISBN: 9783319728520 (print)ISBN: 9783319950211 (print)OAI: oai:DiVA.org:ri-38553DiVA, id: diva2:1314891
Conference
18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 18 August 2019 through 22 August 2019
Available from: 2019-05-10 Created: 2019-05-10 Last updated: 2019-05-10Bibliographically approved

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CiteExportLink to record
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