Charpy impact toughness of martensitic steels irradiated in FFTF: Effect of heat treatment

Technical Report · Thu Dec 31 00:00:00 EST 1992

OSTI ID:139215

Klueh, R L; Alexander, D J ^[1]

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1. Oak Ridge National Lab., TN (United States)

Plates of 9Cr-1MoVNb and 12Cr-1 MoVW steels were normalized and then tempered at two different tempering conditions. One-third-size Charpy specimens from each steel were irradiated to 7.4-8{times}10{sup 26} n/m{sup 2} (about {approximately}35 dpa) at 420{degrees}C in the Materials Open Test Assembly (MOTA) of the Fast Flux Test Facility. Specimens were also thermally aged to 20,000 h at 400{degrees}C to compare the effect of aging and irradiation. Previous work on the steels irradiated to 4-5 dpa at 365{degrees}C in MOTA were reexamined in light of the new results. The tests indicated that prior-austenite grain size, which was varied by different normalizing treatments, had an effect on impact behavior of the 9Cr-1MoVNb but not on the 12Cr-1MoVW. Tempering treatment had relatively little effect on the shift in DBTT for both steels. Conclusions are presented on how heat treatment can be used to optimize properties.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• OSTI ID: 139215
• Report Number(s): DOE/ER-0313/13; ORNL/M-2722; ON: DE93013462; TRN: 93:001624-021
• Resource Relation: Other Information: PBD: [1992]; Related Information: Is Part Of Fusion reactor materials semiannual progress report for period ending September 30, 1992; PB: 378 p.
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION
36 MATERIALS SCIENCE
MARTENSITIC STEELS
HEAT TREATMENTS
PHYSICAL RADIATION EFFECTS
IMPACT STRENGTH
THERMONUCLEAR REACTOR MATERIALS
IRRADIATION
GRAIN SIZE
CHARPY TEST
IRON BASE ALLOYS
CHROMIUM ALLOYS
MOLYBDENUM ADDITIONS
VANADIUM ADDITIONS
NIOBIUM ADDITIONS
TUNGSTEN ADDITIONS
NEUTRON FLUX
DISPLACEMENT RATES
TEMPERATURE RANGE 0400-1000 K
PROGRESS REPORT