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Microstructure of V-4Cr-4Ti Following Low Temperature Neutron Irradiation

Published online by Cambridge University Press:  15 February 2011

P. M. Rice ,
L. L. Snead ,
D. J. Alexander  and
S. J. Zinkle
P. M. Rice
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
L. L. Snead
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
D. J. Alexander
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
S. J. Zinkle
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 3783 1-6376
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Abstract

The V-4Cr-4Ti alloy displays excellent mechanical properties, including a ductile-to-brittle transition temperature (DBTT) below -200°C in the unirradiated condition. Specimens of this alloy were fission neutron-irradiated in the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL) to a dose of 0.4 dpa at temperatures from 100 to 275°C. Mechanical testing showed significant irradiation hardening in the alloy which increased with increasing irradiation temperature. Charpy impact testing also showed a dramatic increase in the DBTT on the order of 200 to 350°c. The mechanical property changes are correlated with preliminary results from the transmission electron microscopy (TEM) analysis of the defect microstructure resulting from the low-dose neutron irradiations. The TEM analysis of the irradiated material showed a nearly constant defect density of ∼1.6 × 1023 m−3, with an average defect diameter of slightly greater than 3 nm.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 439: Symposium B – Microstructure Evolution During Irradiation , 1996 , 343
Copyright
Copyright © Materials Research Society 1997

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