Investigation of Beryllium Corrosion Behaviour in Be-liquid LJ-V4 Ti 4 Cr Alloy System

摘要

One of the advance concepts of breeding blanket for future fusion reactor is the concept of self-cooled lithium-vanadium blanket. In this case beryllium is necessary for providing the tritium breeding efficiency. Corrosion behavior in beryllium - liquid lithium - V-4Ti -4Cr alloy system is the important and at the same time insufficiently investigated aspect of the beryllium application in fusion. The first experimental results on the beryllium corrosion in liquid lithium are presented. Experiments have been performed in V-4Ti-4Cr alloy - liquid lithium static system at the temperatures in the range of 600 - 800℃ during up to 500 hours. The influence of test conditions (temperature, duration, lithium purity and beryllium specimens characteristics including protective beryllium oxide coating) on beryllium corrosion resistance is discussed.