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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...

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Bibliographic Details
Main Author: Del Giacco, Mattia (auth)
Format: Electronic Book Chapter
Language:English
Published: KIT Scientific Publishing 2013
Series:Karlsruher Forschungsberichte aus dem Institut für Hochleistungsimpuls- und Mikrowellentechnik
Subjects:
Technology: general issues
surface aluminizing
Lead cooled reactor
Fretting
corrosion
wear
Online Access:DOAB: download the publication
DOAB: description of the publication
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Description
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

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