1. “Potential Impact of Debris Blockage on Emergency Re-circulation During Design Basis Accidents at Pressurized Water Reactors,” GL 2004-02, U.S. Nuclear Regulatory Commission (Sep. 13, 2004).
2. A diffusion layer model for steam condensation within the AP600 containment
3. Experimental analysis of heat transfer within the AP600 containment under postulated accident conditions
4. “Safety Related Terms for Advanced Nuclear Plants,” IAEATECDOC-626, International Atomic Energy Agency (Sep. 1991).
5. Code of Federal Regulations, Title 10, “Energy,” Part 50, “Domestic Licensing of Production and Utilization Facilities,” Sec. 50.63, “Loss of All Alternating Current Power,” U.S. Nuclear Regulatory Commission (Aug. 28, 2007).