The behavior of low C9Cr2Mo steel in a fast breeder reactor irradiation environment

Tensile testing of EP-823 and HT-9 after irradiation in STIP II

“…Previous work on silicon containing ferritic/martensitic steels showed aging at temperatures from 500 to 600°C led to a decrease in toughness with increasing silicon content caused by precipitation of Laves-phases containing Si and P [8,9]. Such precipitation has also been observed under irradiation at 400°C [10,11]. Similar embrittlement was not observed in reduced activation alloys containing tungsten with very low silicon contents [12].…”

The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels

“…Aging studies performed on the JFMS alloy at temperatures from 500 to 600°C show that Si has a significant effect on toughness caused by precipitation of laves phases containing Si and P [29,30]. Such precipitation has also been observed after irradiation at 400°C [20,21]. Such strong increases in yield strength have also been seen in other high silicon ferritic/martensitic steels.…”

“…Some data points were obtained from an irradiation in EBR-II [20]. The EBR-II irradiation was quoted as a total dose of 3 · 10 26 n/m 2 which was (not knowing the exact position in reactor) translates to $15 dpa using the correlation described by Garner [32].…”

“…These were performed after irradiation in the Japanese Material Test Reactor (JMTR) and FFTF at temperatures from 160 to 520°C [6,7] and doses up to 70 dpa and in the Rotating Target Neutron Source-II (RTNS-II) (14 MeV neutron irradiation) at 20-290°C [8,9]. In addition, microstructural analyses and mechanical tests have been performed after 14 MeV neutron (RTNS-II) [10][11][12], helium [13,14] and aluminum [15] ion, and neutron irradiation in FFTF, JOYO and the Experimental Breeder Reactor-II (EBR-II) [4,[16][17][18][19][20][21] at temperatures from 20 to 650°C.…”