A REVIEW OF IRRADIATION EFFECTS ON MECHANICAL PROPERTIES OF CANDIDATE SCWR FUEL CLADDING ALLOYS FOR DESIGN CONSIDERATIONS

Effects of irradiation on mechanical properties, such as tensile, creep, fatigue, and toughness properties, of candidate Generation IV (Gen IV) super-critical water reactor (SCWR) cladding alloys are surveyed and data are presented with emphasis on direct comparisons of mechanical properties under irradiated and unirradiated conditions for design reference purposes. A brief review of irradiation damage, deformation, and Gen IV SCWR conditions is also provided for quick reference. The survey is by no means exhaustive but it is intended to show the general trend and to serve the need of alloy selection for the fuel cladding. To a lesser extent, the data are also useful for other in-core components of the Canadian pressure-tube type SCWR.