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Division Spotlight
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.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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!
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May 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Haselton
Session Chair:
Baocheng Zhang (Westinghouse Electric Co.)
Session Organizer:
Alternate Chair:
Petri Guimaraes (Studsvik Scandpower)
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Comparison of CASMO-5, MPACT and Serpent 2 for the Modeling of Advanced BWR Lattices
M. Hursin (Paul Scherrer Institute), P. Mala (Paul Scherrer Institute), A. Vasiliev (Paul Scherrer Institute), H. Ferroukhi (Paul Scherrer Institute), Yuxuan Liu (Univ. Michigan), Sooyoung Choi (Univ. Michigan), Brendan Kochunas (Univ. Michigan)
Paper
Demonstration of an Embedded Diffusion Scheme for Modelling the BEAVRS Benchmark Problem
R. H. Prinsloo (Necsa), S.A. Groenewald (Necsa), C. Jacobs (Necsa), D.I. Tomašević (Necsa)
Presented by Kostadin Ivanov (NCSU)
Development and Validation of the GNF Core Simulator Package LANCR02/PANAC11 for the Evaluation of Boiling Water Reactors with LEU+ and High Burn-up Fuel Characteristics
J. Hannah (Global Nuclear Fuel), K. Bennett (Global Nuclear Fuel), G. Cuevas-Vivas (Global Nuclear Fuel), J. Finch (Global Nuclear Fuel), F. Jones (Global Nuclear Fuel), L. Pogosbekyan (Global Nuclear Fuel), B. Ward (Global Nuclear Fuel)
Fuel Cycle Depletion to Spent Fuel Gamma Facility Dose Rate Validation Studies
D. Chandler (ORNL)
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