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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.”
David J. Diamond, Dragan Mirkovic, Chia-Jung Hsu, Robert Fitzpatrick
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 158-165
Technical Paper | Nuclear Reactor Safet | doi.org/10.13182/NT91-A34502
Articles are hosted by Taylor and Francis Online.
Beyond-design-basis overpressurization events in a boiling water reactor are studied to determine if they can lead to catastrophic fuel damage, i.e., fuel fragmentation and the rapid disruption of coolable geometry. This is part of a broader study for the U.S. Nuclear Regulatory Commission to question the adequacy of the events previously selected as the design basis, and to determine if any sequences need more analysis in the context of severe accident research. The RELAP5/MOD2 calculations with failures of the reactor trip and recirculation pump trip, as well as safety and relief valve failures, show that no catastrophic fuel damage is expected. This, in combination with the low frequency of occurrence that can be inferred from the literature, results in a recommendation that no further consideration be given to these events at this time.