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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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A series of firsts delivers new Plant Vogtle units
Southern Nuclear was first when no one wanted to be.
The nuclear subsidiary of the century-old utility Southern Company, based in Atlanta, Ga., joined a pack of nuclear companies in the early 2000s—during what was then dubbed a “nuclear renaissance”—bullish on plans for new large nuclear facilities and adding thousands of new carbon-free megawatts to the grid.
In 2008, Southern Nuclear applied for a combined construction and operating license (COL), positioning the company to receive the first such license from the U.S. Nuclear Regulatory Commission in 2012. Also in 2008, Southern became the first U.S. company to sign an engineering, procurement, and construction contract for a Generation III+ reactor. Southern chose Westinghouse’s AP1000 pressurized water reactor, which was certified by the NRC in December 2011.
Fast forward a dozen years—which saw dozens of setbacks and hundreds of successes—and Southern Nuclear and its stakeholders celebrated the completion of Vogtle Units 3 and 4: the first new commercial nuclear power construction project completed in the U.S. in more than 30 years.
Donald W. Bell
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 245-251
Technical Paper | doi.org/10.13182/NSE60-A25709
Articles are hosted by Taylor and Francis Online.
A study and statistical analysis has been performed on available burnout heat-flux data for vertical upflow of water in uniformly heated rectangular channels at 2000 psia. Two correlating equations were developed with the fluid mass velocity and enthalpy at the burnout location as the two independent variables. It was not found necessary to include the channel length-to-thickness ratio as a third independent variable. The range of variables studied are: 540 to 1000 Btu/lb burnout enthalpy and 0.2 × 106 to 5 × 106 lb/hr-ft2 mass velocity. It is shown that the burnout heat-flux decreases as mass velocity increases for a constant burnout enthalpy in the quality range. Also, a comparison of the developed correlations based upon data for uniformly-heated channels was made with 25 burnout data points for channels having a cosine-shaped axial heat-flux distribution. The cosine data fall on the average of about thirty percent below the burnout heat-flux values for uniformly heated channels under the same coolant conditions at the burnout location.
