Microstructure of V-4Cr-4Ti following low temperature neutron irradiation
Book
·
OSTI ID:541133
- Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.
The V-4Cr-4Ti alloy displays excellent mechanical properties, including a ductile-to-brittle transition temperature (DBTT) below {minus}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 {approximately}1.6 {times} 10{sup 23} m{sup {minus}3}, with an average defect diameter of slightly greater than 3 nm.
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 541133
- Report Number(s):
- CONF-961202--; ISBN 1-55899-343-6
- Country of Publication:
- United States
- Language:
- English
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