Vanadium-base alloys are promising candidate materials for application
in fusion reactor first-wall and blanket structure because of several
important advantages, i.e., inherently low irradiation-induced activi
ty, good mechanical properties, good compatibility with lithium, high
thermal conductivity, and good resistance to irradiation-induced swell
ing and damage. To screen candidate alloys and develop an optimized va
nadium-base alloy, extensive investigations of physical and mechanical
properties of various V-Ti, V-Cr-Ti, and V-Ti-Si alloys have been con
ducted before and after irradiation in lithium environment in fast fis
sion reactors. From these investigations, a V-4Cr-4Ti alloy containing
500-1000 wppm Si and < 1000 wppm O + N + C has been identified as the
most promising alloy, end more comprehensive testing on the performan
ce of this alloy is being conducted for fusion-relevant conditions. Ma
jor results of the comprehensive work to develop the optimal alloy and
test the irradiation performance are presented in this paper. The ref
erence alloy V-4Cr-4Ti exhibited the most attractive combination of th
e mechanical and physical properties that are prerequisite for first-w
all and blanket structures, i.e., good thermal creep behavior, good te
nsile strength and ductility, high impact energy, excellent resistance
to swelling, and very low ductile-brittle transition temperature befo
re and after irradiation. The alloy was highly resistant to irradiatio
n-induced embrittlement in Li at 420-600 degrees C, and the effects of
dynamically charged helium on swelling and mechanical properties were
insignificant. However, several important issues remain unresolved, e
.g., welding, low-temperature irradiation properties, helium effect at
high dose and high helium concentration, irradiation creep, and irrad
iation performance in air or helium environment. Initial results of in
vestigation of some of these issues are also given.