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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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NRC issues Palisades’ draft environmental review, seeks public comment
The Nuclear Regulatory Commission is asking for public comments until March 3 on its environmental assessment (EA) and draft finding of no significant impact at Michigan’s Palisades nuclear power plant, where Holtec hopes to restart operations by the end of 2025.
Technical Session|Sponsored by MCD
Thursday, November 19, 2020|12:15–2:00PM EST
Session Chair:
Katherine E. Royston
Alternate Chair:
Majdi I. Radaideh
Session Organizer:
Brian C. Kiedrowski
Staff Producer:
Ashley Jiminian (American Nuclear Society)
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Data Coverage Assessment on Machine-Learning based Digital Twin for Diagnosis in a Nearly Autonomous Management and Control System
Longcong Wang (North Carolina State University), Linyu Lin (North Carolina State University), Nam T. Dinh (North Carolina State University)
Paper
Uncertainty Quantification Study on EBR-II Benchmark Modeling Strategies using SAM
Travis C. Mui (Argonne National Laboratory), Rui Hu (Argonne National Laboratory)
External Temperature Effects on Thermal Features of Reactor Coolants System and Power Level Estimation
Nageswara S. Rao (Oak Ridge National Laboratory), Christopher Greulich (Oak Ridge National Laboratory), Will Ray (Oak Ridge National Laboratory), Riley Hunley (Oak Ridge National laboratory)
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