Swelling and microstructure of HFIR irradiated austenitic stainless steels

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:6143016

Maziasz, P J

The swelling and microstructural information available from HFIR-CTRs-9-13 are summarized and compared for CW 316 and CW(316 + Ti). These experiments were irradiated to moderate fluences of about 8 to 16 dpa and 500 to 1000 at. ppM He at irradiation temperatures ranging from 285 to 670/sup 0/C. These results are compared to higher fluence HFIR irradiation of CW 316 from HFIR-CTRs-2-8 irradiated at 375 to 680/sup 0/C at fluences up to 61 dpa and 4200 at. ppM He. Both the high- and low-fluence cavity volume fraction swelling curves for CW 316 have a similar shape. The curves show a definite swelling minimum at 470 to 570/sup 0/C that corresponds to the temperature of maximum precipitation. The swelling increases rather sharply with temperature at the higher and lower temperatures. The moderate fluence swelling levels are all below 0.5% ..delta..V/V/sub 0/.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6143016
• Report Number(s): CONF-8009179-3; ON: DE82000158
• Country of Publication: United States
• Language: English

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ALLOYS
AUSTENITIC STEELS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DATA
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HFIR REACTOR
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NICKEL ALLOYS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SWELLING
TANK TYPE REACTORS
TEMPERATURE DEPENDENCE
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS