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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
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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Nuclear Science and Engineering
February 2023
Nuclear Technology
Fusion Science and Technology
Latest News
A review of workforce trends in the nuclear community
The nuclear community is undergoing a moment of unprecedented interest and growth not seen in decades. The passage of the bipartisan Infrastructure Investment and Jobs Act and the Inflation Reduction Act are providing a multitude of new funding opportunities for the nuclear community, and not just the current fleet. A mix of technologies and reactor types are being evaluated and deployed, with Vogtle Units 3 and 4 coming on line later this year, the Advanced Reactor Demonstration Projects of X-energy and TerraPower, and NuScale’s work with Utah Associated Municipal Power Systems to build a first-of-a-kind small modular reactor, making this is an exciting time to join the nuclear workforce.
S. A. Musa, B. Zhao, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 306-311
Technical Paper | doi.org/10.1080/15361055.2017.1333829
Articles are hosted by Taylor and Francis Online.
Experimental evaluation of the thermal-hydraulic characteristics of helium-cooled divertor concepts is important in developing commercial magnetic fusion energy (MFE). Although experimental studies of a variety of concepts have been performed at the Georgia Institute of Technology (GT) over the last decade, achieving prototypical steady-state incident heat fluxes of 10 MW/m2 remains a major challenge. As an alternative to heating the test section, this work presents an initial assessment of a “reversed heat flux approach” that cools the test modules (instead of heating them) with water to determine the heat transfer coefficients (HTC). This approach was pioneered by the Karlsruhe Institute of Technology (KIT) in their initial studies of the helium-cooled modular divertor with multiple jets (HEMJ).
The objectives of this design study are to: 1) determine whether such a reversed heat flux approach can be used to experimentally study the thermal-hydraulic performance of helium-cooled divertor concepts, while minimizing safety and operational issues associated with the extremely high temperatures (>1200°C) reached when testing at prototypical conditions (inlet conditions of 700°C and 10 MPa with an incident heat flux of 10 MW/m2), and 2) determine the design and operational parameters for a small-scale submerged water jet impingement cooling facility suitable for validating these numerical predictions. Numerical simulations were performed to determine the impinging-jet (water) mass flow rates required to remove heat fluxes up to 10 MW/m2 from a single HEMJ module at prototypical conditions (i.e., 700°C and 10 MPa). Initial axisymmetric simulations at water pressures up to 3 MPa suggest that a submerged single-phase impinging water jet at (300 K, 1 MPa) and = 3.5 kg/s can remove heat fluxes as great as 7.5 MW/m2 over a 2 cm diameter area.