Tensile and charpy impact properties of irradiated reduced-activation ferritic steels

Technical Report · Tue Oct 01 04:00:00 EDT 1996

DOI:https://doi.org/10.2172/414868· OSTI ID:414868

Klueh, R. L.; Alexander, D. J. ^[1]

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

Tensile tests were conducted on eight reduced-activation Cr-W steels after irradiation to 15-17 and 26-29 dpa, and Charpy impact tests were conducted on the steels irradiated to 26-29 dpa. Irradiation was in the Fast Flux Test Facility at 365{degrees}C on steels containing 2.25-12% Cr, varying amounts of W, V, and Ta, and 0.1%C. Previously, tensile specimens were irradiated to 6-8 dpa and Charpy specimens to 6-8, 15-17, and 20-24 dpa. Tensile and Charpy specimens were also thermally aged to 20000 h at 365{degrees}C. Thermal aging had little effect on the tensile behavior or the ductile-brittle transition temperature (DBTT), but several steels showed a slight increase in the upper-shelf energy (USE). After {approx}7 dpa, the strength of the steels increased and then remained relatively unchanged through 26-29 dpa (i.e., the strength saturated with fluence). Post-irradiation Charpy impact tests after 26-29 dpa showed that the loss of impact toughness, as measured by an increase in DBTT and a decrease in the USE, remained relatively unchanged from the values after 20-24 dpa, which had been relatively unchanged from the earlier irradiations. As before, the two 9Cr steels were the most irradiation resistant.

• Research Organization: Oak Ridge National Lab., TN (United States)
• OSTI ID: 414868
• Report Number(s): DOE/ER--0313/20; ON: DE97000700
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CHARPY TEST
CHROMIUM ALLOYS
FERRITIC STEELS
NEUTRONS
PHYSICAL RADIATION EFFECTS
PROGRESS REPORT
TENSILE PROPERTIES
TUNGSTEN ALLOYS
VANADIUM ADDITIONS