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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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January 2024
Latest News
Eisenhower’s “Atoms for Peace” at 70
Seventy years ago to the day, President Dwight D. Eisenhower gave his historic address to the United Nations General Assembly in New York City. (See December 2023 Nuclear News's “Leaders” column to read the reflections of Kathryn Huff, the Department of Energy’s assistant secretary for nuclear energy, on the speech’s anniversary.)
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.