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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.”
Efigenio Cubillos-Moreno, Mohamed Belhadj, Tunc Aldemir
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 333-348
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34663
Articles are hosted by Taylor and Francis Online.
The heat flux that leads to onset of nucleate boiling qONB is an important quantity for plate-type research reactors since it is frequently used as a thermal design constraint and also indicates the transition point from single- to two-phase heat removal in transient analyses. Recent experimental work has shown that qONB can be sensitive to both channel gap size d and flow velocity v under laminar, upward flow conditions that are encountered in such reactors under naturalconvection core cooling. New experimental data are presented to test the validity of the correlation proposed from the results of the previous work in extended d and local pressure p ranges. The correlation predicts the new experimental data for mixed or pure buoyancy-driven upward flows in 2.0 ≤ d ≤ 5.0 mm channels with 0.03 ≤ v ≤ 0.16 m/s and 1.05 × 105 ≤ p ≤ 1.70 × 105 Pa within 25%. The new d range covers almost all the existing and planned plate-type research reactors. The p range extends the applicability of the correlation to the analysis of a number of accident scenarios in open-pool reactors with power levels up to 5 to 10 MW, such as partial loss of pool water or coolant pump trip. The pressure range is also relevant to the analysis of similar accidents in higher power pressurized systems if the accident is accompanied by system depressurization. In the implementation of the correlation for such analyses, it is important to note that the correlation implicitly assumes that the wall superheat is nonnegative.
