Precipitation response of austenitic stainless steel to simulated fusion irradiation

Conference · Sat Dec 31 23:00:00 EST 1977

OSTI ID:5149895

Maziasz, P J

The precipitation response of annealed type 316 stainless steel irradiated in HFIR is studied and compared to previously observed thermal aging and fast reactor irradiation responses. Irradiation in HFIR simultaneously produces high levels of helium and displacement damage and partially simulates a fusion environment. Samples have been irradiated at temperatures from 550 to 680/sup 0/C to fluences producing up to 3300 appm He and 47 dpa.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5149895
• Report Number(s): CONF-780213-2
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BARYON REACTIONS
CARBIDES
CARBON COMPOUNDS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYOGENIC FLUIDS
ELEMENTS
FLUIDS
HADRON REACTIONS
HARDENING
HEAT RESISTING ALLOYS
HELIUM
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
MOLYBDENUM ALLOYS
MOLYBDENUM CARBIDES
MOLYBDENUM COMPOUNDS
NEUTRON FLUENCE
NEUTRON REACTIONS
NICKEL ALLOYS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHYSICAL RADIATION EFFECTS
PRECIPITATION HARDENING
PRODUCTION
RADIATION EFFECTS
RARE GASES
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TRANSITION ELEMENT COMPOUNDS