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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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Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
Sven Bader, Ashley Spry (AREVA Federal Services, LLC)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 647-652
A methodology is described that allows for the direct comparison of many diverse objectives with an end result of a rank-ordered evaluation of options that reflects the decision makers' preferences. This methodology, the multi-attribute utility analysis (MUA), is utilized to establish a ranking of routes and associated modes of transport (e.g., truck, rail, barge) to move used/spent nuclear fuel (UNF/SNF) from independent spent fuel storage installations (ISFSIs) to a Class I carrier. Preliminary evaluations have been performed to identify viable modes of transport from some ISFSIs where the only remaining vestige of the reactor site is the ISFSI and hence, very little transportation infrastructure remains at these “stranded” sites for performing these shipments. The MUA is a structured methodology designed to handle the trade-offs among multiple objectives (i.e., attributes) and provides a transparent, rational, and defensible analysis that is easy to explain and communicate and has been used for decades to provide logically consistent analyses of options (i.e., modes and routes) that are intended to achieve more than one objective, where no single option dominates the others on all of those objectives. The ultimate result from the MUA is a list(s) of the most to the least favored/preferred routes from the ISFSI. This paper provides an overview of the MUA methodology and provides examples of its application to several ISFSIs with shutdown reactors.