Development of Inert-Matrix Materials for Pu-Burning or Actinide-Waste Annihilation

Abstract

Significant effort is underway internationally to develop a non-UO₂-based inert-matrix fuel capable of hosting fissile isotopes without generating new plutonium or high-mass carcinogenic actinides. The intention is to be able to dispose of military or reactor-grade plutonium, or eliminate carcinogenic actinides. AECL has a program that focuses on the development of SiC as the candidate material for this new form of fuel; the program includes accelerator-simulation studies of in-reactor behaviour of SiC, fabrication of SiC, compatibility of SiC with water and Zircaloy, waste disposal of SiC, as well as examining reactor physics issues related to SiC. CANDU reactors have been shown to be uniquely suited for this purpose. Results of this AECL program are described.