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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
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Technical Session
Tuesday, May 17, 2022|1:30–3:15PM EDT|Fountainview
Session Chair:
Emre Tatli (Westinghouse Electric Co.)
Alternate Chair:
Nicolas E. Stauff
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Setup and Verification of a SCALE/KENO Platform for Generic FHR Benchmark Calculations
Noah A. Walton (Univ. Tennessee, Knoxville), Robert Crowder (Univ. Tennessee, Knoxville), Vladimir Sobes (Univ. Tennessee, Knoxville), Nader Satvat (Kairos Power), Massimiliano Fratoni (Univ. California, Berkeley), Fatih Sarikurt (Kairos Power), Richard Hernandez (Kairos Power)
Paper
Zero Power Experiment for Molten Salt Reactor -- Code Verification and Validation Request
A. Detkina (Univ. Liverpool), D. Litskevich (Univ. Liverpool), M. Drury (Univ. Liverpool), B. Merk (Univ. Liverpool)
Impact of Nuclear Data Covariance Libraries on Uncertainty Quantification of Sodium Cooled Fast Reactor Simulation
I. Trivedi (INL), K. Zeng (NCSU), J. Hou (NCSU), N. Stauff (ANL)
Sensitivity Analyses of a Homogeneous Model and a RZ Model of the MYRRHA Reactor in its Critical Configuration
Ciro Alfonso (SCK CEN), Pablo Romojaro (SCK CEN), Luca Fiorito (SCK CEN), Augusto Hernandez-Solis (SCK CEN)
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