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3. U.S. Nuclear Regulatory Commission, Preapplication Safety Evaluation Report for the Sodium Advanced Fast Reactor (SAFR) Liquid Metal Reactor, NUREG-1369, December 1991.
4. U.S. Nuclear Regulatory Commission, Preapplication Safety Evaluation Report for the Power Reactor Innovative Small Module (PRISM) Liquid Metal Reactor, NUREG-1368, February 1994.
5. L. E. Strawbridge, “Safety-Related Criteria and Design Features in the Clinch River Breeder Reactor Plant,” Proceedings of the Fast Reactor Safety Meeting, CONF-740401-P1, pp. 72–92, American Nuclear Society, Beverly Hills, CA, April 2–4, 1974.