Recent advances in the treatment of irradiated graphite: A review

Abstract

Graphite is used as a moderator and reflector in nuclear reactors. Fission products and activation of impurities in the graphite contaminated this graphite during reactor operation. Larger amount of irradiated graphite has to be considered as radioactive waste. The management of irradiated graphite waste is becoming an increasingly important issue worldwide. The objective of this paper was to briefly review the recent advances in the treatment and disposal of irradiated graphite to offer deep insight into a better understanding of the techniques for the management of irradiated graphite from nuclear reactors. The properties of irradiated graphite were briefly introduced. The formation of radionuclides, especially C-14, Cl-36 and H-3, in the irradiated graphite was summarized. The main features of Wigner treatment, thermal treatment, chemical treatment, conditioning, coating and impregnation, gasification were addressed. The final end point of the graphite and the final end point of the radionuclides were discussed and their influences on selection of treatment methods were compared.