Evaluation of ferritic alloy Fe-2-1/4Cr-1Mo after neutron irradiation - irradiation creep and swelling

Technical Report · Sat Oct 01 04:00:00 EDT 1983

DOI:https://doi.org/10.2172/6880666· OSTI ID:6880666

Gelles, D S; Puigh, R J

Irradiation creep and swelling measurements are reported for Fe-2-1/4Cr-1Mo after irradiation by fast neutrons over the temperature range 390 to 560/sup 0/C. Diameter change measurements on thin walled pressurized tubes in a bainitic condition and density change measurements on rods in a nonstandard condition were made following irradiation in the Experimental Breeder Reactor II. The irradiation creep specimens were irradiated to a fluence of 5.7 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) or 30 dpa and the swelling specimens were irradiated to a peak fluence of 2.4 x 10/sup 23/ n/cm/sup 2/ or 115 dpa. These results have been used as a basis to establish in-reactor creep and swelling correlations for 2-1/4Cr-1Mo in a bainitic condition. The correlations predict moderate swelling and moderate irradiation enhanced creep at 390/sup 0/C.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6880666
• Report Number(s): HEDL-7405; ON: DE84012368
• Country of Publication: United States
• Language: English

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ALLOYS
BARYONS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CREEP
EBR-2 REACTOR
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
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FAST NEUTRONS
FAST REACTORS
FBR TYPE REACTORS
FERMIONS
HADRONS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STEELS
SWELLING
TEMPERATURE DEPENDENCE
THERMONUCLEAR REACTOR MATERIALS