Irradiation creep and swelling of annealed type 304L stainless steel at @390 degree C and high neutron fluence
Conference
·
OSTI ID:5346677
- Argonne National Lab., IL (USA)
- Pacific Northwest Lab., Richland, WA (USA)
The objective of this effort is to determine the mechanisms involved in radiation-induced deformation of structural materials and apply these insights toward extrapolation of available fast reactor data to fusion-relevant conditions. The irradiation-induced creep and swelling of annealed AISI 304L in EBR-II at {approximately}390{degree}C have been investigated to exposures on the order of 80 dpa and compared with the behavior of AISI 316 stainless steel. It is shown that swelling and creep of various austenitic steels are strongly interactive phenomena. While swelling depends on stress, displacement rate, composition and cold-work level, the creep rate directly depends only on the stress level and the instantaneous swelling rate. The creep-swelling coupling coefficient does not appear to be very sensitive to composition, cold work level or temperature. 14 refs., 6 figs.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC06-76RL01830; W-31109-ENG-38
- OSTI ID:
- 5346677
- Report Number(s):
- PNL-SA-16986; CONF-891204--11; ON: DE90004521
- Country of Publication:
- United States
- Language:
- English
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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
ANNEALING
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CREEP
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LOW CA
MATERIALS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEEL-304L
STAINLESS STEELS
STEEL-CR19NI10-L
STEELS
STRAIN RATE
SWELLING
THERMONUCLEAR REACTOR MATERIALS
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
ANNEALING
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CREEP
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LOW CA
MATERIALS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEEL-304L
STAINLESS STEELS
STEEL-CR19NI10-L
STEELS
STRAIN RATE
SWELLING
THERMONUCLEAR REACTOR MATERIALS