Investigation of Fretting Wear of Cladding Materials in Liquid Lead

Del Giacco, Mattia

Investigation of Fretting Wear of Cladding Materials in Liquid Lead - KIT Scientific Publishing 2013 - 1 electronic resource (XV, 246 p. p.)

Open Access

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 accuracy and reproducibility also during long term tests. Tolerable operating conditions concerning fretting wear by evaluating the specific wear coefficient and the concept of fretting maps are given.


Creative Commons


English

KSP/1000031949 9783866449602

10.5445/KSP/1000031949 doi

surface aluminizing Lead cooled reactor Fretting corrosion wear