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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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!
Latest Magazine Issues
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Technical Session|Sponsored by RPD
Tuesday, June 9, 2020|2:30–4:15PM EDT
Session Chair:
Zeyun Wu (Virginia Commonwealth Univ.)
Alternate Chair:
Pavel V Tsvetkov (LANL)
Session Organizer:
Track Organizer:
Staff Producer:
Jessica Vazquez (American Nuclear Society)
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Advances in MCNP for Reactor Calculations
R. B. Wilkerson (LANL), G. W. McKinney (LANL), C. J. Josey (LANL), M. E. Blood (LANL), J. D. Galloway (LANL), J. C. Armstrong (LANL), H. R. Trellue (LANL)
Paper
Single Channel Design Based on Artificial Intelligence for Molten Salt Reactors
Mehmet Turkmen (Univ. of Illinois), Kathryn D. Huff (Univ. of Illinois)
Development of FRENDY Nuclear Data Processing Code: Generation Capability of Multi-group Cross Sections from ACE File
Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency)
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