Hostname: page-component-78c5997874-94fs2 Total loading time: 0 Render date: 2024-11-18T16:37:36.700Z Has data issue: false hasContentIssue false
  • English
  • Français

Effects of Heavy-Ion Irradiation on Microstructure of V-4Cr-4Ti Alloy at Moderate Temperatures

Published online by Cambridge University Press:  15 February 2011

J. Gazda ,
H. M. Chung ,
B. A. Loomis  and
M. Meshii
J. Gazda
Affiliation:
Northwestern University, Dept. of M.S.&E., Evanston, IL Argonne National Laboratory, Energy Tech Div., Argonne, IL
H. M. Chung
Affiliation:
Argonne National Laboratory, Energy Tech Div., Argonne, IL
B. A. Loomis
Affiliation:
Argonne National Laboratory, Energy Tech Div., Argonne, IL
M. Meshii
Affiliation:
Northwestern University, Dept. of M.S.&E., Evanston, IL
Get access

Abstract

V-4 wt.% Cr-4 wt.% Ti alloy is a promising candidate material for first-wall and structural applications in magnetic fusion reactors. In the past, fast neutron sources were used to evaluate postirradiation properties of fusion candidate materials. The recent shutdowns of the Fast Flux Test Facility (FFTF) and the Experimental Breeder Reactor (EBR-II) left U.S. researchers without local experimental facilities for such tests. Under such circumstances, ease of experimental control, availability, and relatively low cost make heavy-ion irradiation an attractive alternative, provided its limitations are appreciated. We selected 3-MeV V+ and 4.5-MeV Ni++ ions to investigate the effects of irradiation on the microstructure of V-4Cr-4Ti alloy in the temperature range of 200 – 420°C. The main interest is in the evaluation of this alloy's dimensional stability and susceptibility to irradiation embrittlement. In this paper, we report results of ion irradiation experiments and compare them with available data on fast-neutron irradiation. From transmission electron microscopy (TEM) analysis of ion-irradiated specimens, we found that the dominant feature of the postirradiation microstructure was a high density of dislocation loops and pointdefect clusters. Density and defect size depended on irradiation dose and temperature. Precipitates and voids/bubbles were not observed, even in specimens that were simultaneously injected with He and exposed to heavy-ion irradiation. Increased transport of point defects to internal interfaces was observed, as manifested by defect denuded zones along grain boundaries, Defect denuded zones along grain boundaries could lead to segregation of impurities and solutes and formation of precipitates on grain boundaries.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 439: Symposium B – Microstructure Evolution During Irradiation , 1996 , 349
Copyright
Copyright © Materials Research Society 1997

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 Gold, R. E. and Harrod, D. L., Int. Met. Rev. 5/6 (1980) 232 Google Scholar
2 Loomis, B. A. and Smith, D. L., J. Nucl. Mater. 191–194 (1992) 84 Google Scholar
3 Smith, D. L., Loomis, B. A. and Diercks, D. R., J. Nucl. Mater. 135 (1985) 125–139 Google Scholar
4 Geles, D. S., Ohnuki, S., and Takahashi, H., in Fusion Reactor Materials, Semiannual Prog. Report, DOE/ER-0313/20, Oak Ridge National Laboratory, Oak Ridge, TN, (1996), 96–100 Google Scholar
5 Chung, H. M., Nowicki, L. J., and Smith, D. L., in Fusion Reactor Materials, Semiannual Prog. Report, DOE/ER-0313/20, Oak Ridge National LaboratoryOak Ridge, TN, (1996), 84–86 Google Scholar
6 Rowcliffe, A. F., in Fusion Reactor Materials, Semiannual Prog. Report, DOE/ER-0313/20, Oak Ridge National Laboratory, Oak Ridge, TN, (1996), 323–332 Google Scholar
7 Abromeit, C., J. Nucl. Mater. 216 (1994) 78–96 Google Scholar
8 Loomis, B. A., Chung, H. M., Nowicki, L. J., and Smith, D. L., J. Nucl. Mater. 212–215 (1994) 799–803 Google Scholar
9 Chung, H. M., Tsai, H-C., Smith, D. L., Peterson, R., Curtis, C., Wojcik, C., and Kinney, R., in Fusion Reactor Materials, Semiannual Prog. Report, DOE/ER-0313/17, Oak Ridge National Laboratory, Oak Ridge, TN, (1995), 178–182 Google Scholar
10 Ziegler, J. F., TRIM-Transport of Ions in Materials, Version 92, Yorktown, NY, IBM Research.Google Scholar
11 ldquo;Tsai, H-C., Strain, R. V., Hins, A. G., Chung, H. M., Nowicki, L. J. and Smith, D. L., in Fusion Reactor Materials, DOE/ER-0313/17, Oak Ridge National Laboratory, Oak Ridge, TN, (1995), 8–14 Google Scholar
12 Veen, A. van, Eleveld, H., and Clement, M., J. Nucl. Mater. 212–215 (1994) 287 Google Scholar
13 Matsui, H., Kuji, K., Hasegawa, M., and Kimura, A., J. Nucl. Mater. 212–215 (1994) 784 Google Scholar
14 Shikama, T., Ishino, S., and Mishima, Y., J. Nucl. Mater. 69 (1977) 315 Google Scholar
15 Ryazanov, A. I., Manichev, V. M., and Witzenburg, W. van, J. Nucl. Mater. 231 (1996) 304 Google Scholar