Tensile property behavior of irradiated martensitic alloys

Conference · Sat Dec 31 23:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6502756

Klueh, R L ^[1]

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1. Oak Ridge National Lab., TN (USA)

Because chromium-molybdenum martensitic steels have excellent resistance to swelling when irradiated in fast reactors, steels such as 9Cr-1MoVNb and 12Cr-1MoVW are candidates for both fast reactor and fusion reactor applications. To determine the effect of helium on the martensitic steels, nickel-doped 9Cr-1MoVNb and 12Cr-1MoVW steel specimens were irradiated in the High-Flux Isotope Reactor (HFIR). Results were compared with results for undoped steels irradiated similarly and undoped and doped steels irradiated in EBR-II, where little helium was generated. At 300 and 400{degree}C, results indicated that helium affected the strength increase. No helium effect was apparent on specimens irradiated at 500{degree}C. In a second experiment, the 9Cr-1MoVNb and 12Cr-1MoVW steels with and without nickel additions were irradiated in the HFIR at 50{degree}C, the HFIR coolant temperature. Although the strength increases caused by irradiation of the martensitic steels could generally be accommodated by designers, hardening also affects fracture toughness. It is this latter effect that causes the most concern. If helium causes an increase in strength as observed in tensile studies, then such helium could also affect the fracture and impact properties. These studies therefore indicate that, in addition to the displacement damage, the effect of helium must be considered for the design of a fusion reactor.

• OSTI ID: 6502756
• Report Number(s): CONF-891103--
• Journal Information: Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 60; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

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ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL DEFECTS
CRYSTAL STRUCTURE
DESIGN
DISLOCATIONS
DISPLACEMENT RATES
DUCTILITY
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FERRITIC STEELS
FLUIDS
GASES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
HELIUM
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LINE DEFECTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MARTENSITIC STEELS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
NEUTRON FLUX
NEUTRON SOURCES
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
NONMETALS
PARTICLE SOURCES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIATION FLUX
RADIATION SOURCES
RARE GASES
REACTOR MATERIALS
REACTORS
STAINLESS STEELS
STEEL-CR12MOV
STEEL-CR9MONBV
STEELS
TEMPERING
TENSILE PROPERTIES
THERMONUCLEAR REACTORS
TRANSMUTATION
VANA
VANADIUM ADDITIONS
VANADIUM ALLOYS
YIELD STRENGTH