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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Richard B. Stout, Alan H. Robinson
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 86-102
Technical Paper | Fuel Cycle | doi.org/10.13182/NT73-A31344
Articles are hosted by Taylor and Francis Online.
An iterative approach was adopted as the most practical method to search for an optimum fuel loading pattern in pressurized water reactors. A minimum peak-to-average power ratio was chosen as the objective characteristic of the optimum loading. A computer program SHUFLE employs a set of logical shuffling statements which utilizes the radial power shape and reactivity positioning of each iteration to predict a shuffle for the succeeding iteration. Independent logic is employed for different sections of the core and for fuel of relatively high and low reactivity. A two-dimensional simulated two-group coarse-mesh diffusion theory model is utilized to calculate the two-dimensional power distribution after each shuffle. The shuffling logic employed in SHUFLE was demonstrated adequate to predict acceptable loading patterns for initial, equilibrium, and nonequilibrium pressurized water reactor cores.