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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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Technical Session|Sponsored by THD
Wednesday, June 10, 2020|2:30–4:15PM EDT
Session Chair:
Subash L. Sharma (University of Massachusetts, Lowell)
Session Organizers:
Caleb S. Brooks
Alternate Chair:
Rui Hu
Track Organizer:
Igor Bolotnov (NCSU)
Staff Producer:
Janice Lindegard (American Nuclear Society)
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Microreactor Safety Analysis Requirements for Flexible Siting
Rohan Biwalkar (Pittsburgh Technical LLC), Sola Talabi (Pittsburgh Technical LLC), Kenneth Redus (Redus and Associates LLC)
Paper
Presentation Video (Visible to Attendees)
Assessment of the Thermal-Structural Characteristics of Core Components in a Preconceptual Design of the Transformational Challenge Reactor
Casey J. Jesse (INL), James W. Sterbentz (INL), Benjamin R. Betzler (ORNL)
Design of a Flat Channel Experiment to Study Molten Salt Thermal Radiation Heat Transfer
P. Rubiolo (LPSC, Université Grenoble-Alpes), J. Giraud (LPSC, Université Grenoble-Alpes), V. Ghetta (LPSC, Université Grenoble-Alpes), M. Tano (LPSC, Université Grenoble-Alpes), J. Blanco (LPSC, Université Grenoble-Alpes), F. Kovacevich (LPSC, Université Grenoble-Alpes)
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