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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.”
William R. Bohl, Dirk Wilhelm
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 366-373
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34720
Articles are hosted by Taylor and Francis Online.
The origins and goals of the advanced fluid dynamics model (AFDM) program are described, and the models, algorithm, and coding used in the resulting AFDM computer program are summarized. Two boiling pool calculations are presented, the first of an experiment with volume-heated water, the second of a sample fuel/steel pool that is compared with a similar SIMMER-II calculation. A subjective assessment of the AFDM developments is given. It is concluded that a future severe accident code development program might be more oriented toward identification of generic or typical accident sequences rather than attempting to address all uncertainties.