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Erosion-Corrosion experiments on Steels in liquid lead and Development of Slow Strain Rate testing rig
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
2019 (English)Independent thesis Advanced level (degree of Master (Two Years)), 20 credits / 30 HE creditsStudent thesis
Place, publisher, year, edition, pages
2019. , p. 101
Series
TRITA-SCI-GRU ; 2019:369
Keywords [en]
Liquid metal embrittlement, erosion-corrosion, slow strain rate testing-rig, alumina forming alloy, stainless steel, nuclear power, lead cooled reactors, slip.
National Category
Metallurgy and Metallic Materials
Identifiers
URN: urn:nbn:se:kth:diva-261611OAI: oai:DiVA.org:kth-261611DiVA, id: diva2:1359181
Available from: 2019-10-22 Created: 2019-10-08 Last updated: 2019-10-22Bibliographically approved

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