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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
Aaron T. Aoyama, Mohamad Dagher, Russell Feder, Michael Duco, Mahmoud Youssef
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 830-834
Computational Tools, Modeling & Validation | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12489
Articles are hosted by Taylor and Francis Online.
Neutron transport modeling of the ITER reactor structure including modeling the impact of potential neutron streaming along the divertor cassette requires a detailed 3-D CAD solid model of the ITER sector. An all-inclusive, full-scale CAD geometry model of a 40 degree section of the ITER reactor structure was developed for analytical use with the ATTILATM radiation transport code. The source geometry and model used was the reference 1/10th scale A-LITE 3 model provided by the ITER Project Office for radiation transport calculations. Model upscaling, examination, CAD-based cleanup and modifications were performed on each component using the commercial CAD software, SolidWorks. Based on the modified components a new full scale solid model of the ITER section including divertor cassettes was developed in order to ease the implementation of additional diagnostic components being designed by various parties.Geometry repair and modification operations were performed with the goal of obtaining a Parasolid model that would successfully import into and mesh in ATTILA. Many components were re-modeled in order to avoid faulty geometry entities that were identified after the scaling to full-size. This paper will discuss the development of this A-LITE CAD model, and its meshing in ATTILA.