TY  - GEN
AU  - Del Giacco,Mattia
TI  - Investigation of Fretting Wear of Cladding Materials in Liquid Lead
SN  - KSP/1000031949
PY  - 2013///
PB  - KIT Scientific Publishing
KW  - surface aluminizing
KW  - Lead cooled reactor
KW  - Fretting
KW  - corrosion
KW  - wear
N1  - Open Access
N2  - 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
UR  - https://www.ksp.kit.edu/9783866449602
UR  - https://directory.doabooks.org/handle/20.500.12854/50639
ER  -