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...
Saved in:
Main Author: | |
---|---|
Format: | Book Chapter |
Published: |
KIT Scientific Publishing
2013
|
Subjects: | |
Online Access: | Get Fullteks DOAB: description of the publication |
Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
Summary: | 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. |
---|---|
Physical Description: | 1 electronic resource (XV, 246 p. p.) |
ISBN: | KSP/1000031949 9783866449602 |
Access: | Open Access |