Influence of irradiation on the tensile properties of austenitic stainless steel weldments

Conference · Mon Dec 31 23:00:00 EST 1979

OSTI ID:5982967

Wiffen, F W; Edmonds, D P; Horak, J A; King, J F

Weldments in the first wall and front sections of the blanket of a fusion reactor will be exposed to approximately the same operating conditions as will the base metal. Thus the irradiation response of weld metal, of the weld heat affected zones in the base metal, and of the base metal are all of equal concern. Austenitic stainless steels will most likely be joined by a gas tungsten arc welding process. Welds have been made by this process between sections of 6-mm-thick (0.25 in.) base plate of type 316 in the 20%-cold-worked condition, with either type 316 or 16-8-2 stainless steel filler metal. Rod tensile specimens were cut through the welds, containing weld meta in the central gage portion. Weld-contaning tensile specimens have been irradiated in HFIR at 55/sup 0/C and throughout the temperature range 280 to 620/sup 0/C. The neutron fluences ranged from 0.5 to 1.6 x 10/sup 26/ n/m/sup 2/ (> 0.1 MeV). The corresponding displacement damage levels range from 4.5 to 12.1 dpa, and the helium generation from the thermal neutron captures in nickel resulted in 100 to 550 at. ppM He.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5982967
• Report Number(s): CONF-8009179-6; ON: DE81032002
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
AUSTENITIC STEELS
BREEDING BLANKETS
FIRST WALL
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
STEELS
TENSILE PROPERTIES
THERMONUCLEAR REACTOR WALLS
WELDED JOINTS