U.S. Department of EnergyOffice of Scientific and Technical Information
Estimating structural integrity of Type 304 stainless steel plates and pipes containing small defects
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Idaho National Engineering Lab., Idaho Falls (USA)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 6268430
- Report Number(s):
- CONF-790802-11
TRN: 79-014488
- DOE Contract Number:
- EY-76-C-07-1570
- Resource Type:
- Conference
- 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
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 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
Citation Formats
Reuter, W. G. Estimating structural integrity of Type 304 stainless steel plates and pipes containing small defects. United States: N. p., 1979.
Web.
Reuter, W. G. Estimating structural integrity of Type 304 stainless steel plates and pipes containing small defects. United States.
Reuter, W. G. 1979.
"Estimating structural integrity of Type 304 stainless steel plates and pipes containing small defects". United States. https://www.osti.gov/servlets/purl/6268430.
@article{osti_6268430,
title = {Estimating structural integrity of Type 304 stainless steel plates and pipes containing small defects},
author = {Reuter, W. G.},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6268430},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1979},
month = {Mon Jan 01 00:00:00 EST 1979}
}