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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Egile nagusia:	Del Giacco, Mattia
Formatua:	Online
Hizkuntza:	ingelesa
Argitaratua:	KIT Scientific Publishing 2021
Gaiak:	T1-995 surface aluminizing Lead cooled reactor Fretting corrosion wear thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues
Sarrera elektronikoa:	35321
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