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

Continuum modeling of localized deformation in irradiated bcc materials

“…The mechanical behavior of these structural materials is significantly influenced by radiation damage, with effects including an increase in yield point, decrease in uniform ductility and considerably lower true strain to fracture [1][2][3][4][5]. Failure in these materials is governed by heterogeneous localized deformation due to the formation of dislocation channels, wherein majority of the inelastic strain is localized [6][7][8].…”

Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF

“…Over the past few decades, the normalized and tempered HT9 steel (also called the 12Cr-1MoVW steel) has been the most important alloy for the core structures of sodium-cooled fast reactors (SFRs) [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15]. The successful operation of the Fast Flux Testing Facility (FFTF) at Hanford site during 1980-1992 was a monumental demonstration for its in-reactor performance, where the key core components including fuel claddings and ducts are made of HT9 steel [8].…”

Behavior of ferritic/martensitic steels after n-irradiation at 200 and 300°C

“…The selection of F/M steels is based mainly on their mechanical performance based on Charpy and/or tensile testing after irradiation in fast neutron flux irradiation facilities such as FFTF [6], PHE-NIX [7], BOR60 [8] at temperatures higher than 350°C. It is anticipated that this class of steels would exhibit much more hardening and therefore embrittlement after irradiation at lower temperatures [9].…”