/pdf/resolution-of-qualification-issues-for-existing-structural-38g3c2ed86.pdf

Resolution of qualification issues for existing structural materials.

The ferritic (martensitic) steels and the austenitic stainless steels are being considered for use as first wall and blanket structural components for fusion reactors. Tensile specimens of normalized-and-tempered 9 Cr-1 MoVNb and 12 Cr-1 MoVW steels, normalized-and-tempered and isothermally annealed 2-1/4 Cr-1 Mo steel, and 20%-cold-worked type 316 stainless steel were irradiated at approximately 50/sup 0/C to damage levels of up to about 9 displacements per atom (dpa) in the High Flux Isotope Reactor (HFIR). The preirradiated microstructures of the 9 Cr-1 MoVNb and 12 Cr-1 MoVW steels were a tempered martensite; the microstructure of the normalized-and-tempered 2-1/4 Cr-1 Mo steel was tempered bainite, and that of the isothermally annealed 2-1/4 Cr-1 Mo steel was primarily polygonal ferrite.

J.M. Vitek

Papers

Tensile behavior of three commercial ferritic steels after low-temperature irradiation