A number of research and development (R&D) projects have been established to provide thermalhydraulics- and safety-related information in support of the development of the CANDU~(~R) supercritical water-cooled reactor (SCWR). These projects are mainly funded through three separate programs: the Generation-IV national program, the NRCan-NSERC collaborative research and development (CRD) program, and the AECL CANDU-X program. Thermalhydraulics-related projects in these programs focus on the development of heat transfer prediction methods for CANDU-type bundles. These projects cover analytical and experimental studies in supercritical water and surrogate fluids in tubes and bundles. Short descriptions of these projects and the results obtained up to this point are presented.
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