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Radiation Induced Microstructural Evolution in Reactor Pressure Vessel Steels

Published online by Cambridge University Press:  16 February 2011

G. R. Odette
G. R. Odette*
Affiliation:
Departments of Mechanical Engineering and Materials, University of California Santa Barbara, SANTA BARBARA, CA 93106
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Abstract

The evolution of the fine scale microstructural features leading to irradiation embrittlement of reactor pressure vessel steels is described. Copper rich phases undergo accelerated precipitation from supersaturated solution due to radiation enhanced diffusion. In steels with significant trace quantities of copper the precipitates, characterized by high concentrations and small sizes, are the dominant embrittling feature. Precipitate concentrations, sizes, volume fractions and compositions are consistent with thermodynamic and kinetic models that rationalize the effects of a number of irradiation and metallurgical variables. Phosphide and carbonitride phases may also develop along with new manganese nickel rich precipitates, promoted by high nickel contents. These features may lead to severe embrittlement at high fluence even in low copper steels. While their detailed identity and characteristics are not known, defect cluster-solute complexes with a range of thermal stability are important both directly and indirectly; for example, in mediating flux and temperature effects. In conjunction with the application of state-of-the-art characterization methods, development of advanced modeling tools will be needed to address a number of outstanding issues.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 373: Symposium Y – Microstructure of Irradiated Materials , 1994 , 137
Copyright
Copyright © Materials Research Society 1995

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References

REFERENCES

1. Odette, G. R. and Lucas, G. E., An Experimental Investigation of Kinetic Aspects of Neutron Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels, EPRI NP 6114, EPRI, Palo Alto (1989).Google Scholar
2. Odette, G. R. and Lucas, G. E. in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review - II. ASTM STP909, edited by Steele, L. E. (ASTM, Philadelphia, 1986), p. 206.Google Scholar
3. Lucas, G. E. and Odette, G. R. in Proc. Second Int'l Symp. on Environmental Degradation of Materials in Nuclear Reactors - Water Reactors. edited by Roberts, J.T.A., Weeks, J.R. and Theus, G.J. (ANS, LaGrange Park, III, 1986), p. 345.Google Scholar
4. Odette, G. R., Mader, E. V., Lucas, G. E., Phythian, W. J., and English, C. A. in Effects of Radiation on Materials: 16th International Symposium. ASTM STP 1175, edited by Kumar, A. S., Gelles, D. S., Nanstad, R. K., and Little, E. A., (ASTM, Philadelphia, 1993), p. 373.Google Scholar
5. Odette, G. R., Neutron Irradiation Effects in Reactor Presure Vessel Steels and Weldments, (IAEA Technical Report Series, Vienna), in press.Google Scholar
6. Odette, G. R., Scripta Met., 11, 1183 (1983).Google Scholar
7. Phythian, W. J. and English, C. A., J. Nuc. Mat. 205, 162 (1993).Google Scholar
8. Frisius, F., Kampmann, R., Beaven, P. A., and Wagner, R. in Dimensional Stability and Mechanical Behaviour of Irradiated Metals and Alloys- V1, (BNES, London, 1983), p. 171.Google Scholar
9. Beaven, P. A., Frisius, F., Kampmann, R., and Wagner, R. in Proc. Second Int'l SYmp. on Environmental Deeradation of Materials in Nuclear Reactors -Water Reactors. edited by Roberts, J.T.A., Weeks, J.R. and Theus, G.J. (ANS, LaGrange Park, III, 1986), p. 400.Google Scholar
10. Beaven, P. A., Frisius, F., Kampmann, R., Wagner, R., and Hawthorne, J. R. in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review -III.ASTM STP 1011, edited by Steele, L. E., (ASTM, Philadelphia, 1989), p. 243.Google Scholar
11. Fint, J. A., A Study of the Evolution of Precipitates in Pressure Vessel Steels Using Small Angle Neutron Scattering, Master of Science Thesis, Department of Chemical and Nuclear Engineering, University of California, Santa Barbara, 1990.Google Scholar
12. Kampmann, R., Frisius, F., Hackbarth, H., Beaven, P. A., Wagner, R., and Hawthorne, J. R. in Fifth International Symposium on Environmental Degmadation of Materials in Nuclear Power Systems - Water Reactors. edited by Cubicciotti, D., Simonen, E. P., and Gold, R. E., (ANS, La Grange Park, Illinois, 1992), p. 679.Google Scholar
13. Solt, G., Frisius, F., Waeber, W. B., and Tipping, P. in Effects of Radiation on Materials: 16th International Symposium. ASTM STP 1175, edited by Kumar, A. S., Gelles, D. S., Nanstad, R. K., and Little, E. A., (ASTM, Philadelphia, 1993), p. 444.Google Scholar
14. Buswell, J. T., Bischler, P. J. E., Fenton, S. T., Ward, A. E., and Phythian, W. J., J. Nuc. Mat. 205, 198 (1993).Google Scholar
15. Odette, G. R. and co-workers (to be published).Google Scholar
16. Williams, T. J. and Phythian, W. J. in Effects of Radiation on Materials: 17th International Symposium, edited by Gelles, D. S., Nanstad, R. K., Kumar, A. S., and Little, E. A., (ASTM, Philadelphia), to be published.Google Scholar
17. Miller, M. K. and Burke, M. G., J. Nuc. Mat. 195, 68 (1992).Google Scholar
18. Brauer, G., Liszkay, L., Molnar, B., and Krause, R., Nuc Eng.& Des. 12–7, 47 (1991).Google Scholar
19. Mader, E., Odette, G. R., and Lucas, G. E. in Effects of Radiation on Materials: 15th International Symposium, ASTM STP 1125, edited by Stoller, R. E., Kumar, A. S., and Gelles, D. S., (ASTM, Philadelphia, 1992), p. 151.Google Scholar
20. Auger, P., Pareige, P., Akamatsu, M., and Duysen, J. C. Van in Effects of Radiation on Materials: 17th International Symposium, edited by Gelles, D. S., Nanstad, R. K., Kumar, A. S., and Little, E. A., (ASTM, Philadelphia), to be published.Google Scholar
21. Grosse, M., Eichorn, F., Bohmert, J., Brauer, G. in Effects of Radiation on Materials: 17th International Symposium, edited by Gelles, D. S., Nanstad, R. K., Kumar, A. S., and Little, E. A., (ASTM, Philadelphia), to be published.Google Scholar
22. Odette, G. R. and Sheeks, C. K. in Phase Stablity During Irradiation, edited by Holland, J.R., Mansur, L.K. and Potter, D. I., (TMS-AIME, Warrendale, PA, 1981), p.415 Google Scholar
23. Phythian, W. J. (private communication).Google Scholar
24. Hawthorne, J. R., Menke, B. H. and Hiser, A. J. in Effects of Radiation on Materials: 12th International Symposium, ASTM STP 870, edited by Garner, F.A. and Perrin, J. A., (ASTM, Philadelphia, PA, 1985), p. 1163.Google Scholar
25. Pachur, D. and Seivers, G. in Irradiation Program for Pressure Vessel Steels, (KFA Julich, 1974).Google Scholar
26. Jones, R. B. and Buswell, J. T. in Proc. Third Int'l Sy=p. on Environmental Degradation of Materials in Nuclear Reactors - Water Reactors, edited by Theus, G.J. and Weeks, J.R., (TMS, Warrendale, PA, 1988), p. 111.Google Scholar
27. Foreman, A. J. E., Phythian, W. J., and English, C. A., Phil Mag A 66, 671 (1992).Google Scholar
28. Odette, G. R., Lucas, G. E., Klingensmith, D., Stoller, R., and Phythian, W. J., ibid. 16.Google Scholar
29. Ercolessi, F. and Adams, J. B., Europhysics Letters 26, 583 (1994).Google Scholar