REFERENCES
- G.A. PON, W.B. LEWIS, L.R. HAYWOOD, D.B. PRIMEAU, G.J. PHILLIPS, and E.E. MERLO, “Prospective D2O-moderated Power Reactors,” Proc. Intern. Conf. Peaceful Uses At. Energy, Geneva, Vol. 5, P/10, p. 333 (1964).
- G.H. CHALDER, W.T. BOURNS, M.A. FERADAY, and J. VEEDER, “U3Si as a Nuclear Fuel,” AECL-2874. Paper presented at Canadian Nuclear Association Conference, Montreal (May 1967).
- F.H. HUESTON, “The Development of Production Techniques for Uranium Silicide,” OPE-42, Eldorado Mining & Refining Limited, Port Hope, Canada. Paper presented at the Canadian Nuclear Association Conference, Montreal (May 1967).
- M.A. FERADAY, G.H. CHALDER, and K.D. COTNAM, “Irradiation of U3 Si-Interim Results After 7360 MWd/tonne U,” AECL-2684, Atomic Energy of Canada Limited (April 1967).
- A.R. KAUFMANN, B.D. CULLITY, and G. BITSIANES, “Uranium Silicon Alloys,” Trans. AIME, 209, 23 (January 1957).
- L.M. HOWE and L.G. BELL, “Pre-Irradiation Tests on U-Si Alloys,” AECL-646, Atomic Energy of Canada Limited (May 1958).
- L.M. HOWE, “Irradiation Behaviour of Enriched U3Si Elements Sheathed in Zircaloy-2,” AECL-984, Atomic Energy of Canada Limited (1960).
- M.L. BLEIBERG and L.J. JONES, “The Effects of Pile Irradiation on U3Si,” Trans. AIME, 212, 758 (1958).
- J.H. KITTEL and K.F. SMITH, “Effects of Irradiation on some Corrosion Resistant Fuel Alloys,” ANL-5640, Argonne National Laboratory (1960).
- J.F.R. AMBLER, Private Communication at Chalk River Nuclear Laboratory.
- C.L. ANGERMAN and G.R. CASKEY, Jr. “Swelling of Uranium by Mechanical Cavitation,” J. Nucl. Mater., 13, 2, 182 (1964).
- R.D. LEGGETT, T.K. BIERLEIN, B. MASTEL, and H.A. TAYLOR, “Basic Swelling Studies,” BNWLSA-154, Battelle Northwest Laboratories (September 1965).
- Derived by applying (to U3Si/Zircaloy) work reported in AECL-1552, “Heat Transfer Co-efficient Between UO2 and Zircaloy,” (1962) by A.M. ROSS and R.L. STOUTE, and in NYO-2136 (1959), “Thermal Conductance of Metallic Surfaces in Contact,” by H. FENECH and W.M. ROHSENOW.
- Derived from the thermal conductivity of U3Si at 70°C as reported by R.K. McGEARY, Ed., in “Development of Properties of Uranium Base Alloys Corrosion Resistant in High Temperature Water,” WAPD-127-Part 1 (1955). Values extrapolated to fuel operating temperatures assuming that the increase in conductivity in U3Si is similar to that reported for uranium by A.N. HOLDEN in Physical Metallurgy of Uranium, p. 46, Addison-Wesley Publishing Co. Inc.