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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!
Latest Magazine Issues
Mar 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
April 2025
Nuclear Technology
Fusion Science and Technology
Latest News
U.S. and Japan collaborate on high-burnup fast reactor fuel safety tests at INL
Idaho National Laboratory recently conducted a safety test on high-burnup fast reactor fuel from historic irradiation testing at the lab’s Experimental Breeder Reactor-II (EBR-II). According to the Department of Energy, which announced the work March 12, it’s the first such safety test to be performed in over 20 years.
Technology of Fusion Energy (TOFE) 2020 Virtual Meeting
Technical Session|Sponsored by Fusion Energy
Monday, November 16, 2020|3:40–5:50PM EST
Session Chair:
Dennis Youchison (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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Experimental and Numerical Evaluation of the Thermal-Fluid Characteristics of the Helium-Cooled Modular Divertor with Multiple Jets using a Reversed Heat Flux Approach
Shekaib Ahmad Musa (GIT), Minami Yoda, Said I Abdel-Khalik, Daniel S Lee
Paper
Presentation Video (Visible to Attendees)
Updated Thermo-Fluids Performance of the Simplified “Flat” Variant of the HEMJ
Minami Yoda, Said I Abdel-Khalik, Shekaib A Musa, Daniel S Lee (GIT)
Presentation Video (Visible to Attendees) — compressed
Thermo-mechanical design for the design of KSTAR Tungsten Divertor
Sang Woo Kwag, Yang Soo Kim, Hyung Ho Lee, Nak Hyong Song, Yong Bok Chang, Suk-Ho Hong, Hong-Tack Kim, Dr., Sungjin Kwon (NFRI)
Heat Transfer Performance of Cu-Cr-Zr Tube with Swirl Insert Under Cyclic Thermal Loading in Monoblock Divertor
Lane Carasik, Arturo Cabral, Cody Wiggins (VCU)
CFD simulations of helium flow loop test section
Gary Mueller, Arnold Lumsdaine, Charles Kessel, Dennis Youchison, Monica Gehrig (Missouri S&T)
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