ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Ahmet Sozer, Thomas M. Anklam, H. L. Dodds, Jr.
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 452-462
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33502
Articles are hosted by Taylor and Francis Online.
An engineering heat transfer model was developed to predict the total heat transfer coefficients above the froth region in a nuclear reactor core undergoing a slow core uncovering. The model consists of a new heat transfer correlation for convection to steam and a one-dimensional thermal radiation equation. Above the froth region, large wall-to-bulk temperature ratios can take place; therefore, variable property effects on flow and heat transfer were examined because they can affect the heat transfer conditions to a considerable extent. The convective heat transfer coefficients and rod surface temperatures were calculated by using various correlations. The comparison of the results showed that the new correlation accurately predicts the convective heat transfer coefficients and, when combined with the radiation equation, the wall temperatures. The use of this model should be of value in modeling small-break loss-of-coolant accidents and preliminary design work.