METHOD TO PREDICT RELATIVE HYDRIDING WITHIN A GROUP OF ZIRCONIUM ALLOYS UNDER NUCLEAR IRRADIATION

摘要

A method of analyzing outside the reactor to provide the hydriding relative behavior in the reactor of zirconium-based materials. Samples of zirconium-based materials are treated in an autoclave in an aqueous lithium hydroxide solution relatively concentrated (0.3 to 1.0 M) at constant temperatures in the refrigerant temperature range in the reactor water (280-316 ° C). Samples tested by this procedure performed outside the reactor, when compared based on the ratio between the hydrogen weight gain and the oxide weight gain, are used to accurately predict the relative rate of hydrogenation of these materials when they are subjected to corrosion (radiation) in the reactor.