fracture analysis. Volume 1 of welded type 304 stainless steel pipe. J-R curve characterization and limit load analysis
Technical Report
·
OSTI ID:5505418
An experimental investigation was performed to determine the fracture resistance of 4 in. diameter circumferentially welded type 304 stainless pipe at 288/sup 0/C (550/sup 0/F). Two crack geometries were investigated. These were a circumferential through wall crack (simple) and circumferential through wall crack superimposed on a 360 degree radial crack on the inside diameter of the pipe (complex). Test results were analyzed using J-integral and limit load techniques. Additionally, J-integral resistance curve tests were performed on large plansize compact tension specimens for comparison with the pipe specimen results. Results of the J-integral analysis indicate that J-initation for pipes containing simple cracks was approximately 1120 kJ/M/sup 2/(6400 in-lb/in/sup 2/) and a factor of four decrease in J-initiation was noted for pipes containing the complex crack. Good agreement was shown at J-initiation between pipe specimens containing the simple crack geometry and compact tension specimens. The accuracy of the limit load analysis was variable for pipes containing the simple crack geometry with the average predicted limit load calculated using the ASME Code flow stress being 8.7% higher than that actually attained in the tests. The calculated limit loads based on the ASME Code flow stress were conservative for the complex crack cases.
- Research Organization:
- David W. Taylor Naval Ship Research and Development Center, Bethesda, MD (USA)
- OSTI ID:
- 5505418
- Report Number(s):
- NUREG/CR-4538-Vol.1; ON: TI86901465
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
ENERGY SYSTEMS
FLUID FLOW
FRACTURE MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LOADING
MATERIALS
MATERIALS HANDLING
MATHEMATICAL MODELS
MECHANICS
NICKEL ALLOYS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
STRESSES
THERMAL POWER PLANTS
WELDED JOINTS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
ENERGY SYSTEMS
FLUID FLOW
FRACTURE MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LOADING
MATERIALS
MATERIALS HANDLING
MATHEMATICAL MODELS
MECHANICS
NICKEL ALLOYS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
STRESSES
THERMAL POWER PLANTS
WELDED JOINTS