References

1

ASME Boiler and Pressure Vessel Code (1989), Sec. III, Div. 1, App. III, 268-270.

2

ARIES-I Tokamak Reactor Study - Final Report, UCLA-PPG-1323, 8-33-8-35.

3

D. L. Smith et al., Blanket Comparison and Selection Study - Final Report, Argonne National Laboratory, ANL/FPP-84-1 (1984).

4

D. L. Smith, B. A. Loomis and D. R. Diercks, Vanadium-base alloys for fusion reactor applications - a review, J. Nucl. Mater. 135 (1985) 125-139.

5

D. N. Braski, The effect of neutron irradiation on vanadium alloys, J. Nucl. Mater. 141-143 (1986) 1125-1131.

6

M. L. Grossbeck and J. A. Horak, Tensile properties of V-15Cr-5Ti following neutron irradiation and helium implantation, Radiation Effects 101 (1986) 169-171.

7

J. W. Davis, T. A. Lechtenberg, D. L. Smith and F. W. Wiffen, Structural materials data base assessment for the blanket comparison and selection study, Fusion Tech. 8 (1985) 1927-1943.

8

K. C. Liu, High temperature fatigue behavior of unirradiated V-15Cr-5Ti tested in vacuum, J. Nucl. Mater. 103 &104 (1981) 913-918.

9

J. J. Kibler, ``Composite Laminate Analysis System (CLASS),'' Materials Sciences Corp., ASM International, Metals Park, OH (1987).

10

J. W. Holmes, Influence of stress ratio on the elevated-temperature fatigue of a silicon carbide fiber-reinforced silicon nitride composite, J. Am. Ceram. Soc. 74 [7] (1991) 1639-1645.

11

see, for instance, R. C. Juvinall, Fundamentals of Machine Component Design (John Wiley &Sons, New York, 1983) 216-220.