[en] Since next-step fusion devices will be fuelled with mixtures of tritium and deuterium, the knowledge base and tritium handling experience associated with the operation of CANDU reactors is viewed as relevant to the development of safe fusion technology. Fusion safety issues will be compared with fission safety experience, after which specific Canadian activities in support of fusion safety will be overviewed. In addition, recommendations for appropriate fusion safety criteria will be summarized. 18 refs

[en] Ontario Hydro operates a 10,000 MW capacity nuclear power system utilizing the CANDU pressurized heavy water reactor design. The use of D₂O as moderator and coolant results in the production of about 2400 Ci of tritium per MWe-yr. As a result, there is significant Canadian experience in the treatment, handling, transport, and storage of tritiated wastes. Ontario Hydro operates its own reactor waste storage site which includes systems for volume reduction, immobilization and packaging of wastes. In addition, a facility to remove tritium from heavy water is presently being commissioned at the Darlington nuclear site. This facility will generate tritiated liquid and solid waste that will have to be properly conditioned prior to storage or disposal. The nature of these various wastes and the processes/packaging required to meet storage/disposal criteria are judged to have relevance to investigations in fusion facility waste arisings. Experience to date, planned operational procedures and ongoing R and D in this are are described

[en] Short communication

[en] Since next-step fusion devices will be fuelled with mixtures of tritium and deuterium, the knowledge base and tritium handling experience associated with the operation of CANDU reactors is viewed as relevant to the development of safe fusion technology. Fusion safety issues will be compared with fission safety experience, after which specific Canadian activities in support of fusion safety will be overviewed. In addition, recommendations for appropriate fusion safety criteria will be summarized

[en] An international design team comprised of members from the Soviet Union, the United States of America, Japan, the European Community and Canada are in the process of designing an experimental fusion reactor. This project, presently in the conceptual design phase, has been ongoing since May 1988, and is headquartered at the Max Planck Institute for Plasma Physics in Garching, Germany. The performance objectives for the International Thermonuclear Experimental Reactor (ITER) are to demonstrate controlled plasma ignition, extended burn using tritium and deuterium, and in-situ testing of power reactor-relevant materials, systems and technologies. Canadian agencies, coordinated through and including the Canadian Fusion Fuels Technology Project, have made contributions to the present reference design of this device, specifically in the areas of tritium systems, reactor configuration and maintenance, nuclear safety and facility layout. This paper reviews the present status of the ITER project, outlines the depth and breadth of Canadian involvements and contributions, and describes the likely terms of reference for the next design phase. (Author)

No abstract available