D. L. Porter, Ferrite Formation in Neutron-Irradiated Type 304L Stainless Steel, J. Nucl. Mater. 79, pp. 406-411 (1979).
D. L. Porter and F. A. Garner, Swelling of AISI 304L in Response to Simultaneous Variations in Stress and Displacement Rate, ASTM STP-870, pp. 212-220 (1985).
D. L. Porter. G. L. Hofman, B. R. Seidel, and L. C. Walters, Factors Controlling Metal Fuel Lifetime, Proceedings of the International Conference on Reliable Fuels for Liquid Metal Reactors, Tucson. AZ. pp. 4-75 to 4-90 (September 1986).
D. L. Porter and F. A. Garner, Cessation of Irradiation Creep in AISI 316 Concurrent with High Levels of Swelling, ASTM STP 956, pp. 11-21 (1988).
D. L. Porter, C. E. Lahm, and R. G. Pahl, Fuel Constituent Redistribution During the Early Stages of U-Pu-Zr Irradiation, Met. Trans. 21A, pp. 1871-1876 (July 1990).
L. C. Walters, D. L. Porter, D. C. Crawford, Nuclear Fuel Considerations for the 21st Century, Progress in Nuclear Energy, 40, No. 3-4, p 513 (2002).
D.C. Crawford, D. L. Porter, S. L. Hayes, Fuels for Sodium Cooled Fast Reactors, Journal of Nuclear Materials 371 (2007) p. 202-231.
D. L. Porter and C. B. Hilton Extending Sodium Fast Reactor Driver Fuel Use to Higher Temperature, Nuclear Technology, v. 173 (2011) p. 218-225.
D. L. Porter and H. Tsai, Full-length U-xPu-10Zr (x=0,8,19) Fast Reactor Fuel Pin Test in FFTF, Journal of Nuclear Materials, v.427 (2012) p. 46-57.
D. L. Porter, H. J. M. Chichester, P. G. Medvedev, S. L. Hayes and M. C. Teague, “Performance of Low Smeared Density Sodium-cooled Fast Reactor Metal Fuel,” Journal of Nuclear Materials, v.465, (2015), p.464-470.