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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
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.
Joonhong Ahn, Myeongguk Cheon
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 303-319
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3793
Articles are hosted by Taylor and Francis Online.
A linear programming approach has been developed to determine maximum mass loading of radionuclides in vitrified high-level waste (HLW). Linear approximation for the centerline temperature of vertically stacked cylindrical HLW canisters has been developed by assuming constant heat flux from a canister, steady-state heat transfer, natural convection, and by neglecting radiation effects. With the linear formula for the centerline temperature, it has been demonstrated that maximum radionuclide mass loading can be determined by the linear programming model conservatively. A numerical result for vitrification of HLW from PUREX reprocessing of pressurized water reactor spent fuel indicates that the maximum temperature constraint is one of the essential constraints in determining the feasible solution space for optimization if the heat emission from the waste is in a certain range (between 11.2 and 24.5 W/kg in this example).The linear programming model can be utilized to link various fuel cycle models and repository performance models in a consistent and quantitative manner.