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Title: Swelling and tensile properties of neutron-irradiated vanadium alloys

Conference ·
OSTI ID:6133847

Vanadium-base alloys are candidates for use as structural material in magnetic fusion reactors. In comparison to other candidate structural materials (e.g., Type 316 stainless and HT-9 ferritic steels), vanadium-base alloys such as V-15Cr-5Ti and V-20Ti have intrinsically lower long-term neutron activation, neutron irradiation after-heat, biological hazard potential, and neutron-induced helium and hydrogen transmutation rates. Moreover, vanadium-base alloys can withstand a higher surface-heat, flux than steels because of their lower thermal stress factor. In addition to having these favorable neutronic and physical properties, a candidate alloy for use as structural material in a fusion reactor must have dimensional stability, i.e., swelling resistance, and resistance to embrittlement during the reactor lifetime at a level of structural strength commensurate with the reactor operating temperature and structural loads. In this paper, we present experimental results on the swelling and tensile properties of several vanadium-base alloys after irradiation at 420, 520, and 600{degree}C to neutron fluences ranging from 0.3 to 1.9 {times} 10{sup 27} neutrons/m{sup 2} (17 to 114 atom displacements per atom (dpa)).

Research Organization:
Argonne National Lab., IL (USA)
Sponsoring Organization:
DOE/ER
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
6133847
Report Number(s):
CONF-9009264-4; ON: DE91006588; TRN: 91-001932
Resource Relation:
Conference: Conference on the effect of irradiation on materials of fusion reactors, Leningrad (USSR), 18-20 Sep 1990
Country of Publication:
United States
Language:
English