PRISM: An Innovative Inherently Safe Modular Sodium Cooled Breeder Reactor
The Power Reactor Inherently Safe Module (PRISM) is an innovative sodium-cooled breeder reactor concept. The 415 MWe power block is composed of three identical reactor modules each rated at 425 MW of thermal power with separate standardized steam generator systems. The reference 1245 MWe plant employs nine PRISM reactors and three turbine generators when fully developed.
KeywordsFuel Assembly Containment Vessel Decay Heat Power Block Primary Pump
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- 1.R. G. Pahl, et al., “Recent Irradiation Tests of Uranium-Plutonium-Zirconium Metal Fuel Elements,” ANS International Conference on Reliable Fuels for Liquid Metal Reactors, Tucson, AZ, September 7, 1986.Google Scholar
- 2.H. P. Planchon, G. H. Golden, J. I. Sackett, and R. H. Sevy, “Implications of the EBR-II Inherent Safety Demonstration Tests,” Nuclear Engineering and Design, January 1987.Google Scholar
- 3.J. B. Waldo, “The GEM, a Passive Shutdown Feature for LMRs,” ANS Trans., Winter Meeting, Washington, D. C., November 21, 1986.Google Scholar
- 4.U.S. Code of Federal Regulations. Title 10 Part 20. “Standards for Protection Against Radiation” (1985).Google Scholar
- 5.U.S. Nuclear Regulatory Commission. Regulatory Guide 8.8, “Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be As Low as is Reasonably Achievable,” Revision 3, 1978.Google Scholar
- 6.U.S. Code of Federal Regulations. Title 40 Part 190. “Environmental Radiation Protection Standards for Nuclear Power Operations,” (1985).Google Scholar
- 7.U.S. Code of Federal Regulations. Title 10 Part 50, Appendix I. “Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion ‘As Low as is Reasonably Achievable’ for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents,” (1985)Google Scholar