Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environment

Conference · Sun Dec 31 23:00:00 EST 1978

OSTI ID:6259271

Grossbeck, M L; Maziasz, P J

Tensile and fracture properties of type 316 stainless steel in the annealed and 20% cold-worked conditions were investigated to neutron fluences producing 16 dpa and 1000 at. ppM He resulting from irradiation in the High Flux Isotope Reactor. Tensile elongations remained above 6% at 350 and 450/sup 0/C and 4% at 575/sup 0/C. Fracture behavior has been examined in the 20% cold-worked material. At 350/sup 0/C the fracture mode is unchanged by irradiation and is characterized by ductile tearing. At 450/sup 0/C irradiation causes the fracture mode to change from ductile tearing to crystallographic fracture which may occur along the slip bands introduced by the cold working. At 575/sup 0/C the fracture is changed from ductile transgranular to intergranular. The tensile properties observed are believed to be adequate for fusion reactor service within the values of damage parameters investigated.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6259271
• Report Number(s): CONF-790125-50
• 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
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DUCTILITY
FIRST WALL
FRACTURE PROPERTIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NEUTRON FLUENCE
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS