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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nov 2024
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Technical Session|Fundamental Thermal Hydraulics
Thursday, August 24, 2023|10:45AM–12:25PM EDT|Columbia 2
Session Chair:
Roberto Capanna
Alternate Chair:
Philippe M. Bardet
Session Organizer:
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Natural Convection Heat Transfer with Molten Salt in a Differentially-Heated Cavity
10:45–11:05AM EDT
Noah LeFrancois (McGill Univ.), Jovan Nedic (McGill Univ.), Melanie Tetreault-Friend (Hatch)
Paper
A Study of Laminar-Turbulent Transition in Rod Bundles
11:05–11:25AM EDT
L. C. Aldeia Machado (Penn State), C. Bourdot Dutra (Penn State), S. P. Bistany (Penn State), E. Merzari (Penn State)
Zero-Emission Mobile Carbon Capture Facility Powered By Decay Heat of Nuclear Spent Fuels
11:25–11:45AM EDT
Muyue Li (Univ. Michigan), Zhenyu Fei (Univ. Michigan), Kunzhe Bao (Univ. Michigan), Boren Ke (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Lumin Wang (Univ. Michigan)
Mechanistic Modeling of Interfacial Area Transport for Vertical Round Pipes over Wide Range of Pipe Diameters
11:45AM–12:05PM EDT
Zhuoran Dang (Univ. Calgary), Mamoru Ishii (Purdue), Yang Zhao (Purdue)
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