Highlights of Canadian Activities in Fusion Safety

Abstract

A next-step experimental fusion reactor will likely have many of the features of a fusion power reactor except for tritium breeding and electrical power production systems. The proposed International Thermonuclear Experimental Reactor (ITER) will have a total (plasma plus direct heating) power output approaching 2000 MW (thermal). This level of performance (up from the 1 to 2 MW recently demonstrated at JET) requires significant quantities of tritium to be handled inside the facility. Hence, tritium safety is one of the key issues to be addressed in the design. CFFTP is supporting the ITER conceptual design activity by design contributions, primarily to fuel cycle (tritium) related systems. As a result of the tritium safety R and D programs that have been in place for many years, in support of the CANDU program, Canada is a recognized world leader in tritium safety. While CFFTP has utilized fission relevant R and D to the greatest extent possible, some safety R and D programs have been established to address specific fusion safety concerns. In some instances, such programs have been co-sponsored by fusion groups outside Canada. The paper describes the key safety issues associated with experimental fusion devices and how these issues are being addressed by the fusion community and by CFFTP.