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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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!
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Nuclear Science and Engineering
Fusion Science and Technology
Saskatchewan government provides C$80 million for eVinci demonstration
Saskatchewan premier Scott Moe yesterday announced C$80 million (about $59 million) for the Saskatchewan Research Council (SRC) to pursue demonstration of Westinghouse Electric Company’s eVinci microreactor technology.
Technical Session|Sponsored by MCD
Tuesday, June 15, 2021|12:00–1:45PM EDT
Robert E. Grove
Brian C. Kiedrowski
Janice Lindegard (ANS)
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Direct Computation and Moment-Based Reconstruction of Neutron Multiplicity Distributions
Jawad R. Moussa (Univ. of New Mexico), Anil K. Prinja (Univ. of New Mexico)
Perturbation-Theory-Based Sensitivity Analysis of Prompt Neutron Decay Constant for Water-Only System
Tomohiro Endo (Nagoya Univ.), Akihiro Noguchi (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency)
Presentation Video (Visible to Attendees)
Manufactured Solutions for Nonlinear, Coupled Neutronics-Thermalhydraulics Problems for Code Verification
Aya Hamdy Hegazy (Univ. of Illinois Urbana-Champaign), Rizwan-uddin (Univ. of Illinois Urbana-Champaign)
Convergent Transport Source Iteration Calculations with Quasi-Monte Carlo
Samuel Pasmann (Univ. of Notre Dame), Ilham Variansyah (Univ. of Notre Dame), Ryan G. McClarren (Univ. of Notre Dame)
Diffusion Theory for Inhomogeneous Neutron Transport Problems in Slab Geometry
Dean Wang (Ohio State Univ.)
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