SYMPOSIA PAPER Published: 01 January 1987
STP25656S

The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys

Source

Specimens of V-15Cr-5Ti, VANSTAR-7, and V-3Ti-1Si were encapsulated in molybdenum alloy tubes containing 7Li to prevent interstitial pickup and irradiated in the Fast Flux Test Facility (FFTF), using Materials Open Test Assembly (MOTA) experiments, to a damage level of 40 displacements per atom (dpa). The irradiation temperatures were 420, 520, and 600°C. For a better simulation of fusion reactor conditions, helium was preimplanted in some specimens using a modified version of the “tritium trick.” The V-15Cr-5Ti alloy was most susceptible to irradiation hardening and helium embrittlement, followed by VANSTAR-7, and V-3Ti-1Si. VANSTAR-7 exhibited a relatively high maximum void swelling of ∼6% at 520°C while V-15Cr-5Ti and V-3Ti-1Si had values of <0.3% at all three temperatures. The V-3Ti-1Si clearly outperformed the other two vanadium alloys in resisting the effects of neutron irradiation.

Author Information

Braski, DN
Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN
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Details
Developed by Committee: E10
Pages: 271–290
DOI: 10.1520/STP25656S
ISBN-EB: 978-0-8031-5017-1
ISBN-13: 978-0-8031-0963-6