Influence of neutron irradiation at 55/sup 0/C on the properties of austenitic stainless steels

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:6346300

Wiffen, F W; Maziasz, P J

Types 316 and 316 + 0.23 wt % Ti stainless steels and 16-8-2 weldment were irradiated in HFIR at 55/sup 0/C to fluences up to 1.35 x 10/sup 26/ neutrons/m/sup 2/ (< 0.1 MeV), which produced up to 10.5 dpa and 520 at. ppM He. Examination showed no swelling, no cavities, no precipitates, but a high concentration of dislocations. Tensile tests showed large increases in the 35/sup 0/C strength properties, with the weldments the weakest of the materials. The ductility of all materials was reduced by the irradiation, the uniform elongation to only 0.4% in the cold-worked material. Tests at temperatures above the irradiation temperature showed an approach to unirradiated properties as the temperature was increased from 200 to 600/sup 0/C. Helium embrittlement at 700/sup 0/C severely reduced elongation.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6346300
• Report Number(s): CONF-810831-31; ON: DE81028065
• Country of Publication: United States
• Language: English

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ALLOYS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DUCTILITY
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NICKEL ALLOYS
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
TITANIUM ALLOYS