Hostname: page-component-78c5997874-t5tsf Total loading time: 0 Render date: 2024-11-07T20:21:02.092Z Has data issue: false hasContentIssue false

Modeling the Post-Yield Flow Behavior After Neutron and Electron Irradiation of Steels and Iron-Base Alloys

Published online by Cambridge University Press:  15 February 2011

R.J. Dimelfi
Affiliation:
Reactor Engineering Division, Argonne National Laboratory, Argonne, IL 60439, [email protected]
D.E. Alexander
Affiliation:
Materials Science Division, Argonne National Laboratory, Argonne, IL 60439
L.E. Rehn
Affiliation:
Materials Science Division, Argonne National Laboratory, Argonne, IL 60439
Get access

Abstract

Irradiation hardening is an issue of practical importance as it relates to the remanent life and the nature of failure of reactor components exposed to displacement-producing radiation. Understanding these phenomena requires studies of fundamental microstructural mechanisms of hardening. In this paper, we analyze the tensile behavior of pressure vessel steels (A212B and A350) irradiated by neutrons and electrons. The results show that the post-yield true stress/true strain behavior can provide fingerprints of the different hardening effects that result from irradiation by the two particles, which suggests correspondingly different hardening microstructures for the two particles. Microstructurally-based models for irradiation-induced yield strength increases, combined with a model for strain hardening, are used to make predictions of the different effects of irradiation by the two particles on the entire flow curve that agree well with data.

Type
Research Article
Copyright
Copyright © Materials Research Society 1999

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Seeger, A., Proc. 2 d United Nations Int. Conf. on the Peaceful Uses of Atomic Energy, Geneva, United Nations, New York, 1958, p. 250.Google Scholar
2. Olander, Donald R., Fundamental Aspects of Nuclear Reactor Fuel Elements, NTIS, Springfield, VA, 1976, pp. 418462.Google Scholar
3. Blewitt, T.H., Dislocations and Mechanical Properties of Crystals, Ed. by Fisher, J.C., Wiley, New York, 1956, p.573.Google Scholar
4. Pachur, D., Proc. 109h Int. Symp. On Effects of Radiation on Materials, ASTM STP 725, Ed. by Kramer, D., Brager, H.R. and Perrin, J.S., Philadelphia, PA, 1981, p.5.Google Scholar
5. Farrell, K., Mahmood, S.Y., Stoller, R.E., Mansur, L.K., J. Nucl. Mater. 210, p. 268 (1994).Google Scholar
6. Makin, M.J. and Minter, F.J., Acta Met. 8, p. 691 (1960).Google Scholar
7. Makin, M.J. and Blewitt, T.H., Acta Met. 10, p. 241 (1962).Google Scholar
8. Odette, G.R., Liu, C.L., Wirth, B.D., Proc. Symp. On Microstructure Evolution During Irradiation, Ed. by Robertson, I.M., Was, G.S., Hobbs, L.W. and Rubia, T.D.de la, MRS, Pittsburgh, 1997, pp. 457469.Google Scholar
9. Odette, G.R., Proc. Symp. on Microstructure of Irradiated Materials, Ed. by Roberston, I.M., Rehn, L.E., Zinkle, S.J. and Phythian, W.J.., MRS, Pittsburgh, (1994) pp. 137148.Google Scholar
10. Rice, P.M. and Stoller, R.E., J. Nucl. Mater. 244, pp 219226 (1996).Google Scholar
11. DiMelfi, R.J., Alexander, D.E. and Rehn, L.E., J. Nucl. Mater. 252, pp 171177 (1997).Google Scholar
12. Alexander, D.E. and Rehn, L.E., J. Nucl. Mater. 217, p. 213 (1994).Google Scholar
13. Pareige, P., Stoller, R.E., Russell, K.F. and Miller, M.K., J. Nucl. Mater. 249, pp. 165174.Google Scholar
14. Eason, E.D., Wright, J.E., Nelson, E.E., Odette, G.R. and Mader, E.V., Nucl. Eng. Des. 179, pp. 257265.Google Scholar
15. Pareige, P., Russell, K.F., Stoller, R.E. and Miller, M..K., J. Nucl. Mater. 250, pp. 176183 (1997).Google Scholar
16. Alexander, D.E., Odette, G.R., Lucas, G.R. and Rehn, L.E., Proc. Symp. On Thermodynamics and Kinetics of Phase Transformations, Ed. Im, J.S., Park, B., Greer, A.L., Stephenson, G.B., MRS, Pittsburgh, PA, 1995, pp. 177182.Google Scholar
17. English, C.A., Phythian, W.J., McElroy, R.J., Symp. On Microstructure Evolution During Irradiation, Ed. by Robertson, I.M., Was, G.S., Hobbs, L.W. and Rubia, T.D. de la, MRS, Pittsburgh, 1997, pp. 471482.Google Scholar
18. DiMelfi, R.J., Alexander, D.E. and Rehn, L.E., Proc. 6th Int. Conf. on Nuclear Engineering, ICONE-6, ASME, New York, 1998, paper no.6079.Google Scholar
19. Oak Ridge National Laboratory Technical Report, ORNIJIM- 10444, Evaluation of HFIR Pressure Vessel Integrity Considering Radiation Embrittlement, Ed. by Cheverton, R.D., Merkle, J.G. and Nanstad, R.K., April, 1988, p. 118.Google Scholar
20. Voce, E., J. Inst. Met. 74 p.537 (1968).Google Scholar
21. Whapham, A.D. and Makin, M..J., Phil. Mag. 5, p. 237 (1960).Google Scholar
22. Mott, N.F., J. Inst. Met. 72, p. 367 (1946).Google Scholar