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Title: Tensile behavior of helium-implanted and neutron-irradiated V-15 Cr-5 Ti

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5723001

Vanadium alloys are being considered for use for the first-wall and blanket structures in fusion reactors due to their high melting points and low neutron activation. The allow reported on here, V-15 Cr-5 Ti, was prepared by the Westinghouse Advanced Reactors Division (Heat HSV-307). Since the fusion environment produces helium in all common structural alloys including vanadium, the effect of helium in irradiated alloys was investigated. In a fusion reactor spectrum, /approx/5 at. ppm He/dpa is expected. Ideally, the helium should be produced concurrently with displacement damage. However, since this is difficult or impossible in vanadium without a source of high-energy neutrons, cyclotron implantation of helium followed by fission reactor irradiation was chosen. By this method, it was hoped to scope qualitatively the effect of helium alone and the synergistic effect of helium in conjunction with neutron irradiation. It was concluded that: 1. Cyclotron injection of 80 at. ppm He has little effect on mechanical properties of V-15 Cr-5 Ti at 700 and 625/degree/C and causes a factor of /approx/2 reduction in elongation at 400/degree/C. 2. Neutron irradiation to 24 to 32 dpa increases the strength of annealed V-15 Cr-5 Ti by a factor or /approx/2 and decreases ductility by a factor of about 10. 5 refs., 2 figs.

Research Organization:
Oak Ridge National Lab., TN (USA)
OSTI ID:
5723001
Report Number(s):
CONF-860610-
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15-20 Jun 1986
Country of Publication:
United States
Language:
English