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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.
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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.”
Shlomo Ron, Judah Tzoref
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 37-49
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A35532
Articles are hosted by Taylor and Francis Online.
The potential release of fission products during a beyond-design accident in a medium-sized high-temperature gas reactor (the HTR-500) is investigated. The DSNP modular simulation code is used to simulate a depressurization accident as well as the failure of the forced circulation of the decay heat removal systems to actuate. For such an extreme accident, the calculated maximum localized fuel temperature reaches 3040° C 43 h after the beginning of the accident. During the heatup, 3.4% of the 137Cs inventory is found to be released from the fuel elements to the primary circuit, and 4.6 × 10−2% is estimated to be released into the environment. The carbon monoxide and helium releases from the graphite matrix prove to be an important factor in sweeping the fission products from the primary circuit. The comparative consequence analysis indicates a much lower risk than in the analogous light water reactor severe accident. A design-base depressurization accident is also investigated at the beginning of the study and involves the operation of one out of the two redundant decay heat removal systems.