Analysis of the effects of corrosion potential and impurities on the stress corrosion cracking of Type 304 stainless steel [electronic resource].
- Published:
- Argonne, Ill. : Argonne National Laboratory, 1985.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: 17 : digital, PDF file
- Additional Creators:
- Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- Intergranular stress corrosion cracking (IGSCC) of sensitized Type 304 stainless steel (SS) has been a recurrent problem in the high-temperature water environment of boiling-water-reactors (BWRs) over the past two decades. The synergistic effects of environmental and material variables on stress corrosion cracking (SCC) of Type 304 SS were investigated at 289/sup 0/C by means of constant-extension-rate-tensile (CERT) tests at a strain rate of 1 x 10/sup -6//s. Correlations among environmental variables (dissolved oxygen and impurity concentrations, viz., H/sub 2/SO/sub 4/, steady-state open-circuit electro-chemical potential) and the SCC susceptibility parameters have been determined. The extensive results over a wide range of open-circuit corrosion potential conditions were analyzed by a model which accounts for the effects of environmental variables, microstructure (e.g., degree of sensitization) and strain rate. The results are consistent with a slip-dissolution mechanism for SCC. Furthermore, representation of the dependence of corrosion potential and average crack growth rate on the dissolved oxygen concentration of the water by a simple mathematical function, in conjunction with the theoretical model, enables predictions of both strain rate and environmental effects on the SCC susceptibility of sensitized Type 304 SS. 12 refs., 7 figs.
- Report Numbers:
- E 1.99:conf-850902-2
conf-850902-2 - Subject(s):
- Other Subject(s):
- Bwr Type Reactors
- Reactor Cooling Systems
- Reactor Materials
- Intergranular Corrosion
- Stress Corrosion
- Stainless Steel-304
- Crack Propagation
- Destructive Testing
- Electric Conductivity
- High Temperature
- Mathematical Models
- Oxygen
- Quantity Ratio
- Alloys
- Chemical Reactions
- Chromium Alloys
- Chromium Steels
- Chromium-Nickel Steels
- Cooling Systems
- Corrosion
- Corrosion Resistant Alloys
- Electrical Properties
- Elements
- Energy Systems
- Heat Resistant Materials
- Heat Resisting Alloys
- Iron Alloys
- Iron Base Alloys
- Materials
- Materials Testing
- Nickel Alloys
- Nonmetals
- Physical Properties
- Reactor Components
- Reactors
- Stainless Steels
- Steels
- Testing
- Water Cooled Reactors
- Water Moderated Reactors
- Note:
- Published through SciTech Connect.
06/01/1985.
"conf-850902-2"
"TI85014964"
2. international symposium on environmental degradation of materials in nuclear power systems--water reactors, Monterey, CA, USA, 9 Sep 1985.
Maiya, P.S.; Ruther, W.E.; Kassner, T.F. - Funding Information:
- W-31-109-ENG-38
View MARC record | catkey: 14462818