Tensile properties of 2-1/4Cr-1Mo steel irradiated to 23 dpa at 390 to 550/sup 0/C

Technical Report · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5526745

Klueh, R L; Vitek, J M

The effect of neutron irradiation on the tensile properties of normalized-and-tempered 2-1/4Cr-1Mo steel was determined for specimens irradiated to 23 dpa in the Experimental Breeder Reactor II (EBR-II) at 390, 450, 500, and 550/sup 0/C. Two types of unirradiated control specimens were tested: as-heat-treated specimens and as-heat-treated specimens thermally aged for 10,000 h at the irradiation temperatures. Aging caused a loss of strength at all four temperatures. Irradiation at 390/sup 0/C increased the strength and decreased the ductility compared to the control specimens. At 500 and 550/sup 0/C, softening occurred relative to the thermally aged specimens, with the amount of softening greatest at 550/sup 0/C. At 450/sup 0/C, the strength of the irradiated specimens was similar to a specimen aged 10,000 h at 450/sup 0/C. The changes in tensile properties result from the displacement damage caused by the irradiation and by irradiation-induced changes in carbide precipitates that occur during elevated-temperature exposure.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5526745
• Report Number(s): DOE/OR/21400-T99; ON: DE85015551
• Country of Publication: United States
• Language: English

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ALLOYS
BARYON REACTIONS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
DATA
DUCTILITY
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HADRON REACTIONS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICAL PROPERTIES
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STEELS
TENSILE PROPERTIES