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...
| Format: | eBook |
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| Language: | English |
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KIT Scientific Publishing
2013
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| Series: | Karlsruher Forschungsberichte aus dem Institut für Hochleistungsimpuls- und Mikrowellentechnik
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| Online Access: | Open Access: DOAB: description of the publication Open Access: DOAB, download the publication |