Explore
Investigation of Fretting Wear of Cladding Materials in Liquid Lead
Mattia Del Giacco
2013
0 Ungluers have
Faved this Work
Login to Fave
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.
This book is included in DOAB.
Why read this book? Have your say.
You must be logged in to comment.
Rights Information
Are you the author or publisher of this work? If so, you can claim it as yours by registering as an Unglue.it rights holder.Downloads
This work has been downloaded 27 times via unglue.it ebook links.
- 27 - pdf (CC BY-NC-ND) at Unglue.it.
Keywords
- Corrosion
- Fretting
- Lead cooled reactor
- surface aluminizing
- wear
Links
DOI: 10.5445/KSP/1000031949Editions