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Division Spotlight
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
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
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Karl Britsch, Mark Anderson
Nuclear Technology | Volume 206 | Number 11 | November 2020 | Pages 1625-1641
Critical Review | doi.org/10.1080/00295450.2019.1682418
Articles are hosted by Taylor and Francis Online.
Interest in molten salts for next-generation nuclear reactors has led to increasing design work over the last several years. Much of this builds off historic heat transfer experiments like those of the Molten Salt Reactor Program; however, there is no comprehensive report covering experimental heat transfer in these fluids. This paper attempts to pull together all available reports on fluoride salt heat transfer to aid further research in this area. The data largely support the hypothesis that molten salt heat transfer will be easy to predict so long as salt properties are well known. This paper does not show any consistent indications of resistive films, entrained gases, or radiation heat transfer, but other unknowns are present. In addition to salt properties, these include unusual mass transfer and transition flow conditions.