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Irradiation Creep Behavior of the Fusion Heats of HT9 and Modified 9Cr-1 Mo Steels

R.J. Puigh, F.А. Garner

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Abstract

In-reactor creep data on the fusion heats of HT9 and a modified 9Cr-1Mo steel have been obtained from irradiation of pressurized tube specimens in the FFTF reactor. These irradiations were conducted on specimens which reached /approximately/50 dpa at 400--540/degree/C and which utilized hoop stresses ranging from 0 to 200 Mpa. The creep behavior of these two alloys was found to be similar and to be consistent with creep data on related alloys irradiated in either EBR-II or FFTF. A correlation describing the irradiation-induced creep component of deformation has been developed and compared to the available data. These ferritic steels were also shown to exhibit a superior resistance to creep and swelling at temperatures <520/degree/C when compared to that of the AISI 316 and PCA austenitic alloys also irradiated in the fusion materials program. 18 refs., 5 figs., 2 tabs.

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What this paper is about

In-reactor creep data on the fusion heats of HT9 and a modified 9Cr-1Mo steel have been obtained from irradiation of pressurized tube specimens in the FFTF reactor. These irradiations were conducted on specimens which reached /approximately/50 dpa at 400--540/degree/C and which utilized hoop stresses ranging from 0 to 200 Mpa. The creep behavior of these two alloys was found to be similar and to be consistent with creep data on related alloys irradiated in either EBR-II or FFTF. A correlation describing the irradiation-induced creep component of deformation has been developed and compared to the available data. These ferritic steels were also shown to exhibit a superior resistance to creep and swelling at temperatures <520/degree/C when compared to that of the AISI 316 and PCA austenitic alloys also irradiated in the fusion materials program. 18 refs., 5 figs., 2 tabs.

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Available abstract

In-reactor creep data on the fusion heats of HT9 and a modified 9Cr-1Mo steel have been obtained from irradiation of pressurized tube specimens in the FFTF reactor. These irradiations were conducted on specimens which reached /approximately/50 dpa at 400--540/degree/C and which utilized hoop stresses ranging from 0 to 200 Mpa. The creep behavior of these two alloys was found to be similar and to be consistent with creep data on related alloys irradiated in either EBR-II or FFTF. A correlation describing the irradiation-induced creep component of deformation has been developed and compared to the available data. These ferritic steels were also shown to exhibit a superior resistance to creep and swelling at temperatures <520/degree/C when compared to that of the AISI 316 and PCA austenitic alloys also irradiated in the fusion materials program. 18 refs., 5 figs., 2 tabs.

Key concepts: Creep, Materials science, Irradiation, Austenite, Metallurgy, Fusion power, Deformation (meteorology), Austenitic stainless steel

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Irradiation Creep Behavior of the Fusion Heats of HT9 and Modified 9Cr-1 Mo Steels — Research Paper | ScholarLens