Removal of ~(14)C from Irradiated Graphite for Waste Volume Reduction and Bulk Graphite Recycle: Thermal Treatment

摘要

Nuclear power contributes 20% of the electricity used around the world today. To improve the efficiency of future nuclear power production, the U.S. and other countries are developing advanced nuclear systems coined "Generation IV concepts" as established by the Generation IV International Forum, which institutes protocol for individual countries to lead the development of a concept in which they have particular interest [1]. The U.S. Department of Energy commissioned the Idaho National Laboratory to develop the High Temperature Gas-Cooled Reactor (HTGR). The HTGR uses graphite coated fuel particles, graphite reflector and core structural components, and helium coolant [2].