Estimating structural integrity of Type 304 stainless steel plates and pipes containing small defects
In recent years there has been considerable demand for accurate assessment of the influence of defects on reactor structural component integrity. Analyses used must account for the effect of large plastic deformation of low-strength ductile materials. A number of models have been developed for the analysis of reactor coolant piping as well as less ductile plate and piping, but these models have not been verified for the full spectrum of potential materials and configurations encountered in reactor components. The paper presents preliminary test program results and some evaluation of these models, specifically, the flow stress approach and the two-parameter fracture criterion (TPFC). The tests were conducted with annealed Type 304 stainless steel flat tensile specimens containing triangular, rectangular, or part-circular surface flaws, and pressurized pipe specimens with internal or external triangular surface defects.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6268430
- Report Number(s):
- CONF-790802-11; TRN: 79-014488
- Resource Relation:
- Conference: International conference on structural mechanics in reactor technology, Berlin, F.R. Germany, 13 Aug 1979
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
REACTOR COMPONENTS
DEFORMATION
DEFECTS
MECHANICAL TESTS
STAINLESS STEEL-304
TENSILE PROPERTIES
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
NICKEL ALLOYS
STAINLESS STEELS
STEELS
TESTING
220200* - Nuclear Reactor Technology- Components & Accessories
360103 - Metals & Alloys- Mechanical Properties