Puigh, Raymond J.
Manager, Westinghouse Hanford Company, Richland, WA
Garner, Frank A.
Staff Scientist, Pacific Northwest Laboratory, Richland, WA
Pages: 10 Published: Jan 1990
In-reactor creep data on the fusion heats of HT9 and a modified 9Cr-1Mo steel have been obtained from the irradiation of pressurized tube specimens in the FFTF reactor. These irradiations were conducted on specimens that reached approximately 50 dpa at 400 to 540°C and that used hoop stresses ranging from 0 to 200 MPa. The creep behavior of these two alloys was found to be similar to and consistent with creep data on related alloys irradiated in either EBR-II or the Fast Flux Test Facility (FFTF). A correlation describing the irradiation-induced creep component of deformation has been developed and compared with the available data.
These ferritic steels were also shown to exhibit a superior resistance to creep and swelling at temperatures less than 520°C when compared with AISI 316 and PCA austenitic alloys also irradiated in the Fusion Materials Program.
irradiation creep, fusion heats, ferritic steels, austenitic steels, swelling
Paper ID: STP49472S