Overview of Reactor Systems and Operational Environments for Structural Materials in Gen-IV Fission Reactors

Identifying Limitations of ASME Section III Division 5 For Advanced SMR Designs

“…Molten fluoride and chloride salts offer attractive characteristicssuch as high volumetric heat capacities and high boiling pointto be used as coolants for nuclear reactor [75]. However, they are highly corrosive for many structural alloys, especially alloys with high chromium content which are subject to depletion of chromium into the salt [70].…”

Microstructure Characterization and Hardening Evaluation of Ferrite/Martensitic Steels Induced by He2+ Irradiation

“…Ferrite/martensitic (F/M) steels are of increasing interest and have prospective applications as structural materials in the field of nuclear reactors owing to their superior thermal conductivity, thermal expansion, and resistance to helium radiation-induced swelling and embrittlement [1][2][3]. In fusion or fission reactors like lead-cooled fast reactors (LFR), structural materials will be directly exposed to more severe service environments than existing commercial fission reactors, such as liquid lead-bismuth eutectic (LBE) corrosion, high temperatures (about 500-550 • C), and high neutron irradiation (50-150 dpa) [4]. Therefore, it is important for the use of F/M steels in LFR to take into account the resistance to irradiation embrittlement and irradiation swelling, LBE dissolution corrosion and corrosion embrittlement, besides the excellent high-temperature mechanical properties, including high strength and good elongation.…”