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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
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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
J. C. Rivas, A. de Blas, J. Dies, L. Sedano
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 687-691
Test Blanket, Fuel Cycle, and Breeding | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19172
Articles are hosted by Taylor and Francis Online.
In this work, a model has been developed to calculate the neutron wall loading poloidal distribution in a generic tokamak plasma and vessel geometry on the basis of Monte Carlo simulation. Different neutron source radial profiles corresponding to advanced plasma scenarios have been implemented in this model, using combinations of step and parabolic functions.The model has been validated with data from state-of-the-art simulations of ITER wall loading, and a parametric study has been performed over different plasma geometries and radial profiles to check the variability of the neutron poloidal profile.The results show the effect of the different configurations on neutron wall loading. This model can be used for parametric studies for conceptual design or systems analysis activities.