Testing Methods for Graphite Exposed to Molten Salt Reactor Environment

Abstract

As one of the preferred designs in Generation IV reactors, the molten salt reactor (MSR) is gaining a lot of interest around the world. The MSR uses molten salt as a coolant to transfer heat out from its reactor core. Components of the MSR would be inevitably damaged by both irradiation and molten salt erosion. Nuclear graphite, as a moderator and reflector for the MSR, may receive more irradiation dose than other nuclear materials inside the reactor core. Graphite is also a porous material, and impregnation of molten salts may cause damage to its internal structure. Moreover, the effects of molten salt impregnation are more uncertain due to the change of material properties by irradiation. Here, potential problems in using graphite in the MSR are reviewed. Experimental methods for nuclear graphite exposed to a molten salt environment are also discussed.