Estimates of time-dependence fatigue behavior of type 316 stainless steel subject to irradiation damage in fast breeder and fusion power reactor systems. [Fluence 1--2. 63 x 10/sup 26/ n/m/sup 2/ (E > 0. 1 MeV/ at 593/sup 0/C]

Conference ·

OSTI ID:6825388

Brinkman, C. R.; Liu, K. C.; Grossbeck, M. L.

Cyclic lives obtained from strain controlled fatigue tests at 593/sup 0/C from specimens irradiated to a fluence of 1 to 2.63 x 10/sup 26/ n/m/sup 2/ (E greater than 0.1 MeV) were compared to predictions based on the method of strainrange partitioning. When appropriate tensile and creep-rupture ductilities were employed reasonably good estimates of the influence of hold periods and irradiation damage on the fully reversed fatigue life of type 316 stainless steel could be made. Ductility values for 20 percent cold-worked type 316 stainless steel specimens irradiated in a mixed spectrum fission reactor were used to estimate fusion reactor first wall lifetime. The ductility values were from irradiations that simulate the environment of the first wall of a fusion reactor. Neutron wall loadings ranging from 2 to 5 MW/m/sup 2/ were used. Results, although conjectural because of the many assumptions, tended to show that 20 percent cold-worked type 316 stainless steel could be used as a first wall material meeting a 7.5 to 8.5 MW-year/m/sup 2/ lifetime goal provided the neutron wall loading does not exceed more than about 2 MW/m/sup 2/. Results were obtained for an air environment, and it is expected that the actual vacuum environment will extend lifetime beyond 10 MW-year/m/sup 2/.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6825388
• Report Number(s): CONF-780722-8; TRN: 79-000273
• Resource Relation: Conference: 9. symposium on effects of radiation in structural materials, Richland, WA, USA, 10 Jul 1978
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
FIRST WALL
SERVICE LIFE
STAINLESS STEEL-316
PHYSICAL RADIATION EFFECTS
TOKAMAK TYPE REACTORS
COLD WORKING
CREEP
DAMAGING NEUTRON FLUENCE
DUCTILITY
ELONGATION
FATIGUE
REACTOR COMPONENTS
RUPTURES
STRAIN RATE
TENSILE PROPERTIES
THERMAL STRESSES
WALL LOADING
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
FABRICATION
FAILURES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS WORKING
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NEUTRON FLUENCE
NICKEL ALLOYS
POWER DENSITY
RADIATION EFFECTS
STAINLESS STEELS
STEELS
STRESSES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
360106* - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties
700201 - Fusion Power Plant Technology- Blanket Engineering