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Report Date: July 2001
Appendices: No
Abstract
A review is presented of the ongoing US research activities to develop better understanding about the corrosion aspects of advanced nuclear systems using heavy liquid metal, especially lead and lead-bismuth eutectic, as their coolant. Current understanding of corrosion mechanisms and ongoing as well as planned experimental activities dealing with the compatibility of structural materials with heavy metal coolants are reviewed. This includes facilities at MIT, Los Alamos National Laboratory, Idaho National Engineering and Environmental Laboratory, and Argonne National Laboratory. The operating capabilities of these facilities are compared with regard to temperature, velocity and oxygen control. The needs for further data on both traditional and advanced materials are identified.
Program: ANP : Advanced Nuclear Power Program
Type: TR
RPT. No.: 80