1. “Advanced Nuclear Power,”;BETHE,1973
2. R. F. HILBERT, et al, “Swelling of UC and UN at High Temperatures,” Proceedings of the Conference on Fast Reactor Fuel Element Technology, April 13–15, 1971, New Orleans, Louisiana, American Nuclear Society, pp. 753–769.
3. A. A. BAUER, et al, “Mixed-Nitride Fuel Irradiation Performance,” loc cit, pp. 785–817.
4. A. B. G. WASHINGTON, “Preferred Values for the Thermal Conductivity of Ceramic Nuclear Fuels,” TRG-Memo-5883 (May, 1972).
5. “Nitride Fuels: Properties and Potentials,”;BAUER;Reactor Technology,1972