An Innovative Approach to Nuclear Reactor Design Certification

[+] Author and Article Information
N. W. Brown, M. A. Smith

Astro-Space Division, General Electric Company, San Jose, CA 95153-5354

G. L. Gyorey, B. K. Genetti

Advanced Nuclear Technology, General Electric Company, San Jose, CA 95153-5354

J. Eng. Gas Turbines Power 110(2), 161-165 (Apr 01, 1988) (5 pages) doi:10.1115/1.3240095 History: Received August 07, 1987; Online October 15, 2009


General Electric has proposed that the US Nuclear Regulatory Commission (NRC) consider adding an Appendix to 10CFR50 that would specifically address NRC Safety Review and Design Certification of advanced reactors through use of an experience building test program. The proposal was made in conjunction with the Department of Energy (DOE)-sponsored review of the General Electric advanced Liquid Metal Reactor (LMR) concept, Power Reactor Inherently Safe Module (PRISM). This paper provides a description of the proposed new 10CFR50 Appendix. It also provides the basis for the proposed new approach to Design Certification and outlines the plans that are in place for further review and consideration by the NRC.

Copyright © 1988 by ASME
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