Prediction of aging degradation of cast stainless steel components in LWR systems [electronic resource].
- Published
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (18 pages) : digital, PDF file
- Additional Creators
- Argonne National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- A procedure and correlations are presented for predicting Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of aged cast stainless steels from known material information. The saturation'' impact strength and fracture toughness of a specific cast stainless steel, i.e., the minimum value that would be achieved for the material after long-term service, is estimated from the chemical composition of the steel. Mechanical properties as a function of time and temperature of reactor service are estimated from impact energy and flow stress of the unaged material and the kinetics of embrittlement, which are also determined from chemical composition. The J{sub IC} values are determined from the estimated J-R curve and flow stress. Examples of estimating mechanical properties of of cast stainless steel components during reactor service are presented. A common predicted lower-bound' J-R curve for cast stainless steels of unknown chemical composition is also defined for a given grade of steel, ferrite content, and temperature.
- Report Numbers
- E 1.99:anl/cp-75791
E 1.99: conf-920375--24
conf-920375--24
anl/cp-75791 - Subject(s)
- Other Subject(s)
- Bwr Type Reactors
- Reactor Components
- Pwr Type Reactors
- Stainless Steels
- Aging
- Physical Radiation Effects
- Embrittlement
- Fracture Properties
- Mechanical Properties
- Alloys
- Enriched Uranium Reactors
- High Alloy Steels
- Iron Alloys
- Iron Base Alloys
- Power Reactors
- Radiation Effects
- Reactors
- Steels
- Thermal Reactors
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
03/01/1992.
"anl/cp-75791"
" conf-920375--24"
"DE92014848"
Aging research information conference, Rockville, MD (United States), 24-27 Mar 1992.
Chopra, O.K. - Funding Information
- W-31109-ENG-38
View MARC record | catkey: 14461000