Evaluation of ferritic alloy Fe-2-1/4Cr-1Mo after neutron irradiation - microstructure development

Technical Report · Tue May 01 04:00:00 EDT 1984

DOI:https://doi.org/10.2172/7120109· OSTI ID:7120109

Gelles, D S

Microstructural examinations are reported for nine specimen conditions of 2-1/4Cr-1Mo steel which had been irradiated by fast neutrons over the temperature range 390 to 510/sup 0/C. Two heats of material were involved, each with a different preirradiation heat treatment, one irradiated to a peak fluence of 5.1 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) or 24 dpa and the other to 2.4 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV) or 116 dpa. Void swelling is found following irradiation at 400/sup 0/C in both conditions and to 480/sup 0/C in the higher fluence conditions. Concurrently dislocation structure and precipitation formed. Peak void swelling, void density, dislocation density and precipitate number density developed at the lowest temperature, approx. 400/sup 0/C, whereas mean void size, and mean precipitate size increased with increasing irradiation temperature. The examination results are used to provide interpretation of in-reactor creep, density change and post irradiation tensile behavior.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 7120109
• Report Number(s): HEDL-7447; ON: DE84012376
• Country of Publication: United States
• Language: English

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ALLOYS
BARYONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CRYSTAL STRUCTURE
ELEMENTARY PARTICLES
FAST NEUTRONS
FERMIONS
HADRONS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MICROSTRUCTURE
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STEELS
SWELLING
TEMPERATURE DEPENDENCE
THERMONUCLEAR REACTOR MATERIALS