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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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Technical Session
Monday, October 4, 2021|1:20–3:00PM EDT
Session Chair:
Kostadin Ivanov (NC State Univ.)
Session Organizers:
Benoit Forget (MIT)
William Wieselquist (ORNL)
Student Producer:
K. Lisa Reed (Georgia Tech)
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A Simple Reactor Core Simulator Based on VTT's Kraken Computational Framework
1:20–1:45PM EDT
Ville Valtavirta (VTT Technical Research Centre of Finland), Riku Tuominen (VTT Technical Research Centre of Finland)
Paper
Molten Salt Reactor Depletion Techniques in the ADDER Reactor Depletion and Fuel Management Analysis Code
1:45–2:10PM EDT
A. G. Nelson (ANL), G.J.Y. Chee (Univ. of Illinois Urbana-Champaign), M. G. Jarrett (ANL)
Development of a General MPI Coupling Interface for Multi-Physics Analysis
2:10–2:35PM EDT
A. Abarca (NC State Univ.), M. Avramova (NC State Univ.), K. Ivanov (NC State Univ.)
Modernization of ORIGEN Library Creation in the SCALE Computer Code
2:35–3:00PM EDT
S. Hart (ORNL), W. Wieselquist (ORNL), A. Holcomb (ORNL)
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