REFERENCES
- W. R. GRIMES, “Chemical Research and Development for Molten Salt Breeder Reactors,” ORNL CF-66-7-41, ORNL (1966).
- R. G. MILLS, et al., “A Fusion Power Plant,” MATT-1050, Princeton University (1974).
- R. W. MOIR, et al., “Helium Cooled, Flibe Breeder, Beryllium Multiplier Blanket,” Fusion Technology, Vol. 8, No. 1, Part 1, 1985.
- D. K. SZE, et al., An Assessment of Problems Associated with Tritium Containment,” Fusion Technology, Vol. 8, No. 2, Part 1, 1985.
- J. R. KEISER, et al., “Compatibility of Molten Salts with Type 316 SS and Lithium,” Proceedings of the First Topical Meeting of Fusion Reactor Materials, Miami Beach, FL., January 29–31, 1979.
- G. T. CHENG, GA Technology, Private Communication
- D. L. SMITH, et al., “Vanadium - Base Alloy for Fusion Reactor Applications,” To be published in Journal of Nuclear Materials.
- W. F. CALOWAY, “Electrochemical Extraction of Hydrogen from Molten LiF-LiBr and its Application to Liquid Lithium Fusion Reactor Blanket Processing,” Nucl. Technol. 39, 63 (1978).