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Crack growth behaviour of irradiated type 304L Stainless steel in simulated BWR environment
Studsvik Nuclear AB.
KTH, Superseded Departments (pre-2005), Solid Mechanics.ORCID iD: 0000-0003-1498-5691
2003 (English)In: 11th Int. Conf. on Env. Degradation of Mat. in Nuclear Power Systems – Water ReactorsAt: Stevenson, WA, USA, 2003Conference paper, Published paper (Other academic)
Place, publisher, year, edition, pages
2003.
Keywords [en]
Irradiation effects, Crack growth, Environmentally assisted degradation, Stress corrosion cracking
National Category
Other Materials Engineering
Research subject
Materials Science and Engineering
Identifiers
URN: urn:nbn:se:kth:diva-264033OAI: oai:DiVA.org:kth-264033DiVA, id: diva2:1371795
Conference
11th Int. Conf. on Env. Degradation of Mat. in Nuclear Power Systems – Water ReactorsAt: Stevenson, WA, USA
Note

QC 20191121

Available from: 2019-11-20 Created: 2019-11-20 Last updated: 2019-11-21Bibliographically approved

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CiteExportLink to record
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