Hostname: page-component-8448b6f56d-dnltx Total loading time: 0 Render date: 2024-04-24T17:24:57.096Z Has data issue: false hasContentIssue false
  • English
  • Français

Microstructural and Mechanical Property Changes in Model Fe-Cu Alloys

Published online by Cambridge University Press:  16 February 2011

Philip M. Rice ,
Roger E. Stoller ,
Barry N. Lucas  and
Warren C. Oliver
Philip M. Rice
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6376, (USA)
Roger E. Stoller
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6376, (USA)
Barry N. Lucas
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6376, (USA)
Warren C. Oliver
Affiliation:
Nano Instruments Inc., P.O. Box 14211, Knoxville, TN 37914, (USA)
Get access

Abstract

This paper describes a technique developed to determine values for the dislocation barrier strength of the defects believed to be responsible for the embrittlement of light water reactor (LWR) pressure vessel steels. Microstructures consisting of a single defect type were introduced by ion irradiation or thermal annealing, and the defect distributions were determined by TEM. Hardness changes were measured using a nano indenter and the dislocation barrier strengths for the defects involved were computed based on a dispersed barrier hardening model.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 373: Symposium Y – Microstructure of Irradiated Materials , 1994 , 149
Copyright
Copyright © Materials Research Society 1995

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

REFERENCES

1. Stoller, R. E., “Pressure Vessel Embrittlement Predictions Based on a Composite Model of Copper Precipitation and Point Defect Clustering,” to be published by ASTM, Philadelphia.Google Scholar
2. Odette, G. R., Scripta Met. 17, 1183 (1983).Google Scholar
3. Oliver, W.C., and Pharr, G.M., J. Mater. Res. 7 (6), 1564 (1992).Google Scholar
4. Mace, J. and Phythian, W.J., “AEA/UCSB Model FeCuMn Alloys Results Compendium: Grain Size and 550°C Age Hardening Response,” AEA-RS-2148, AEA Harwell Laboratory, U.K., 1991.Google Scholar
5. Biersack, J.P. and Haggmark, L.G., Nuc. Instr. and Methods 174, 257 (1980).Google Scholar
6.ASTM E521-89, Neutron Radiation Damage Simulation by Charged-Particle Irradiation, ASTM Book of Standards 12.02, (1990).Google Scholar
7. Bement, A. L. Jr, in Strength of Metals and Alloys, Proc. of 2nd Int. Conf., ASM International, Metals Park, OH, 1973, pp. 693–728 Google Scholar
8. Kocks, U.F., Met. Trans. 1, 1121 (1970).Google Scholar
9. Cahoon, J.R., Broughton, W.H., and Kutzak, A.R., Met. Trans. 2, 1979 (1971).Google Scholar
10. Haggag, F.M., Nanstad, R.K., and Braski, D.N., in Innovative Approaches to Irradiation Damage, and Fracture Analysis, edited by Marriott, D.L., Mager, T.R., and Bamford, W.H. (ASME Book No. H00485, 1989) PVP 170, pp.101–107.Google Scholar
11. Kojima, S., Zinkle, S. J., and Heinisch, H. L., J. Nucl. Mater. 179–181, 982 (1991).Google Scholar
12. Othens, P.J., Jenkins, M.L., Smith, G.D., and Phythian, W.J., Phil. Mag. Lett. 64, 383 (1991).Google Scholar