Modeling and quantitative prediction of environmentally assisted cracking based upon a deformation-oxidation mechanism

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 479, Issue , 2004, Pages 175-184

  Shoji, Tetsuo ^a   Wang, Shengchun ^a   Lu, Zhanpeng ^a   Takeda, Yoichi ^a   Peng, Qunjia ^a   Kai, Akira ^a  

^a TOHOKU UNIVERSITY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITIC ALLOYS; OXIDATION MECHANISM; PRIMARY LOOP RECIRCULATION (PLR); QUANTITATIVE PREDICTIONS;

COMPUTER SIMULATION; CRACK INITIATION; DEFORMATION; DEGRADATION; ELASTIC MODULI; OXIDATION; PRESSURIZED WATER REACTORS; STRAIN RATE;

STRESS CORROSION CRACKING;

EID: 7744241704     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2004-2662     Document Type: Conference Paper

References (26)

1. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, NACE, Houston, TX.
2. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, Houston, TX pp.881-889.
3. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, ANS, La Grange Park, IL, pp.588-598.
4. Ford F. P., 1996, "Quantitative Prediction of Environmentally Assisted Cracking," Corrosion, Vol. 52, pp375-395.
5. Shoji T., Lu Z.P., Peng Q.J., 2003, "Experimental and Numerical Approaches for Characterizing the Crack Growth Behavior of Alloy 600 in PWR Primary Water, and Life Time Predictions for Welded Structures." Vessel Penetration Inspection, Crack Growth and Repair Conference, Gaithersburg, MD, USA.
6. Birks N. and Meier G. H., 1983, Introduction to High Temperature Oxidation of Metals. Edward Arnold, London, p.42.
7. Badini C., Laurella F., 2001, "Oxidation of FeCrAlY alloy: influence of temperature and atmosphere on scale growth, rate and mechanism," Surface and Coating Technology. Vol. 135, pp. 291-298.
8. Heusler K. E., 1997, "Fundamental Aspects of Corrosion of Alloys," Corrosion Science. Vol. 39, pp.1177-1191.
9. th International Conference on Fracture, France, Vol.2, pp.669-682.
10. Gerberich W. W., Davidson D. L., and Kaczorowski M., 1990, "Experimental and Theoretical Strain Distributions for Stationary and Growing Cracks," J. Mechanics and Physics of Solids, Vol.38, pp.87-113.
11. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, La Grange Park, IL, pp. 855-861.
12. S. Wang, N. Kawaguchi and T. Shoji, 2004, "Effects of Ce, Y and Mo Addition on the Stress Accerated Oxidation of Austenitic Stainless Steel in Oxygenated High Temperature Water", 2004 International Congress on Advances in Nuclear Power Plants (ICAPP'04), Paper #4228, Pittsburgh, USA.
13. th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 10-14, 2003, Washington, USA, American Nuclear Society, CD-ROM, pp.611-616.
14. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 10-14, 2003, Stevenson, Washington, USA, Paper No. 72424. pp. 1049-1061.
15. Kanetani R., Master's thesis, 2002, Machine Intelligence and Systems Engineering, Graduate School of Engineering, Tohoku University, Japan.
16. th International Conference on Nuclear Engineering, Paper No. ICONE12-49400
17. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, La Grange Park, IL, pp. 834-844.
18. Andresen P. L., Angeliu T. M., Young L. M. 2001, "Effect of Martensite and Hydrogen on SCC of Stainless Steels and Alloy 600," Corrosion'2001, NACE, Houston, TX, Paper No. 228.
19. th International Symposium. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, Skamania. pp.845-854.
20. Speidel M. O. and Magdowski R., 2000, "Stress Corrosion Crack Growth in Alloy 600 Exposed to PWR and BWR Environments," Corrosion'2000, NACE, Houston, TX. Paper 222.
21. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, La Grange Park, IL, pp. 712-719.
22. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Power Water Reactors, ANS, La Grange Park, IL, pp. 333-338.
23. Andresen P. L., 1991, "Fracture Mechanics Data and Modeling of Environmental Cracking of Nickel-Base Alloys in High Temperature Water," Corrosion, Vol. 47(12), pp. 917-938.
24. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, Houston, TX, pp. 541-551.
25. Documents presented at 5th Structural Integrity Evaluation Committee, NISA, Feb. 18, 2003.
26. Wong FMG., Mitchell N. A., Kato T., Nakajima H., Randall R., Morra M., 1998, "Characterization of Incoloy 908 and Avoidance of Stress Accelerated Grain Boundary Oxidation (SAGBO) during ITER Model Coil Fabrication," Fusion Technology, Vol.34, pp.815-821.