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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
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.