Investigation of Fretting Wear of Cladding Materials in Liquid Lead

One promising concept for future nuclear reactors uses liquid metals like Pb as reactor coolant. In this work, fretting of fuel clad materials is investigated in Pb environment at relevant operating conditions. A novel test apparatus is presented that allows fretting tests in liquid lead with high a...

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Bibliographic Details
Superior document:Karlsruher Forschungsberichte aus dem Institut für Hochleistungsimpuls- und Mikrowellentechnik
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Year of Publication:2013
Language:English
Series:Karlsruher Forschungsberichte aus dem Institut für Hochleistungsimpuls- und Mikrowellentechnik
Physical Description:1 electronic resource (XV, 246 p. p.)
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