Development of Inert-Matrix Carrier Fuels for Burning Plutonium or Actinide Waste

Abstract

CANDU reactors are well-suited to utilize carrier fuels to bum excess Pu or actinide waste, because of their excellent neutron economy and fuel-management capabilities. The selection process for determining a good candidate(s) for the carrier matrix is in its early stages. SiC appears to be an excellent choice, because of its high thermal conductivity and resistance to oxidation and interaction with water coolant even at high temperatures, as well as its lack of neutron absorption. Resistance to fission-fragment damage and other issues relevant to its use as a fuel for CANDU reactors are being investigated.