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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Mar 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
Technology of Fusion Energy (TOFE) 2020 Virtual Meeting
Technical Session|Sponsored by Fusion Energy
Tuesday, November 17, 2020|4:50–6:30PM EST
Session Chair:
Arnie Lumsdaine (ORNL)
Staff Producer:
Mary Tong (American Nuclear Society)
To access the session recording, you must be logged in and registered for the meeting.
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Heat transport augmentation using vibration material excited by boiling bubbles for heat removal from divertor
Noriyuki Unno (Tokyo University of Science), Shin-ichi Satake (Tokyo University of Science), Jun Taniguchi, Kazuhisa Yuki
Paper
W emissivity and surface temperature in ITER
Dominique Guilhem (CEA Cadarache)
Predicted Heat Flux Performance of Actively Cooled Tungsten-Armored Graphitic Foam Monoblocks
Douglas Wolfe (ARL/PSU), Brian Williams (Ultramet, Inc.), James Klett (ORNL), Dennis Youchison (ORNL)
Reference — Summary
Determining the poloidal distribution W sourcing by light impurities and heating method in the fully W PFC in WEST
C. C. Klepper, W. R. Wampler, E. Tsitrone, J.-Y. Pascal, A. L. Neff, J. P. Gunn, N. Fedorczak, C. Desgranges, G. Ciraolo, A. Gallo, Ezekial Unterberg (ORNL)
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