Kinetic Measurements for the Carbothermic Synthesis of UN, PuN, and (U,Pu)N

Author:

GREENHALGH W. O.

Publisher

Wiley

Subject

Materials Chemistry,Ceramics and Composites

Reference13 articles.

1. 1 J. F. Fletcher and J. Greenborg , “Nitride Fuels for Fast Breeder Reactors; Fuel Cycle Considerations,” Tech. Rept. BNWL-606, Feb 1968; 100 pp.

2. Development of Mixed-Nitride Fuel Materials Obtained by Carbothermic Reduction of Oxides;Weber;Trans. Amer. Nucl. Soc.,1968

3. 3 W. O. Greenhalgh and E. T. Weber , “Carbothermic Synthesis of a Mixed Uranium-Plutonium Nitride,” Tech. Rept. BNWL-SA-1886, Aug. 1968; 12 pp.

4. 4 E. T. Weber and W. O. Greenhalgh , “Method of Preparing a Nitride Nuclear Reactor Fuel,” U.S. Pat. 3,510,434, May 5, 1970.

5. 5 T. A. Gens , “Thermodynamic Calculation of the Yield of Uranium Nitride During Carbothermic Reduction of Uranium Oxide in the Presence of Pure Nitrogen or Nitrogen Mixed with Hydrogen or Inert Gas,” Tech. Rept. ORNL-TM-1264, Sept. 16, 1965; 16 pp.

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