Fatigue behavior of type 316 stainless steel irradiated in a mixed spectrum fission reactor forming helium

Journal Article · Wed Sep 01 04:00:00 EDT 1982 · Nucl. Technol.; (United States)

OSTI ID:5843388

Grossbeck, M L; Liu, K C

In a Tokamak reactor that operates in a cyclic mode, thermal stresses will result in fatigue in structural components, especially in the first wall and blanket. There has been limited work on fatigue in irradiated alloys, but none on irradiated materials containing irradiation-induced helium, which will be characteristic of fusion service. Specimens of 20% cold-worked Type 316 stainless steel were irradiated in the High Flux Isotope Reactor, which produces atomic displacement damage as well as helium through a two-step neutron absorption reaction with nickel. The specimens were irradiated at 430/sup 0/C to up to 15 dpa and 900 at. ppm helium. Following irradiation, specimens were tested in a vacuum at the irradiation temperature with total strain ranges from 0.30 to 2.0%. The irradiated specimens exhibited a reduction in fatigue life of a factor of 3 to 10 compared to unirradiated material. An endurance limit was observed at a total strain range of 0.3% for irradiated material.

• Research Organization: Oak Ridge National Laboratory, Metals and Ceramics Division, Oak Ridge, Tennessee 37830
• OSTI ID: 5843388
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 58:3; ISSN NUTYB
• 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
ABSORPTION
ALLOYS
BARYON REACTIONS
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
ELEMENTS
ENERGY ABSORPTION
ENRICHED URANIUM REACTORS
FATIGUE
FLUIDS
FRACTURE MECHANICS
GASES
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HELIUM
HFIR REACTOR
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICS
MEDIUM VACUUM
METALS
MOLYBDENUM ALLOYS
MORPHOLOGICAL CHANGES
NATIONAL ORGANIZATIONS
NEUTRON REACTIONS
NICKEL
NICKEL ALLOYS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
ORNL
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RARE GASES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SLIP
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
STRESSES
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
THERMAL STRESSES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WALLS
WATER COOLED REACTORS
WATER MODERATED REACTORS