TY  - BOOK
AU  - Del Giacco, Mattia
AB  - 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.
DO  - 10.5445/KSP/1000031949
ID  - OAPEN ID: 35321
KW  - surface aluminizing
KW  - Lead cooled reactor
KW  - Fretting
KW  - corrosion
KW  - wear
L1  - https://www.ksp.kit.edu/9783866449602
LA  - English
LK  - https://directory.doabooks.org/handle/20.500.12854/50639
PB  - KIT Scientific Publishing
PY  - 2013
SN  - 9783866449602
TI  - Investigation of Fretting Wear of Cladding Materials in Liquid Leadnull
ER  - 
