1. Uranium Nitride Fuel Development;DeCrescente,1965
2. S. C. Weaver, J. L. Scott, R. L. Senn, B. H. Montgomery, USAEC report ORNL-4461, Oak Ridge National Laboratory, 1969.
3. Mixed-nitride fuel irradiation performance;Bauer,1971
4. Analysis of experimental data on gas release and swelling of UN fuel irradiated in BR-10 reactor;Porollo,2017
5. An equation that describes fission gas release from UN reactor fuel;Storms;J. Nucl. Mater.,1988