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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Stanley H. Levinson, Robert S. Enzinna, B&W Nuclear Service Company, P.O. Box 10935, Lynchburg, Virginia 24506-0935
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 102-111
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34446
Articles are hosted by Taylor and Francis Online.
The Babcock & Wilcox and United Engineers and Constructors advanced light water reactor (ALWR) design has features that will provide enhanced safety, reliability, and design margin over the current generation of commercial nuclear power plants. The B-600 ALWR is a 600-MW(electric) two-loop pressurized water reactor (PWR). A probabilistic analysis has been performed to provide early feedback to the designers to enhance the reliability of the safety systems. Based on this information, the ALWR designers have eliminated most of the features that dominate the risk profile in conventional PWRs. This has resulted in the calculated core damage frequency for the ALWR being better than the design targets.
