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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Thomas Moore, Mike Steer, Marco Delchini, Mathieu Martin, Brian Woods
Nuclear Technology | Volume 206 | Number 6 | June 2020 | Pages 862-894
Technical Paper | doi.org/10.1080/00295450.2019.1667186
Articles are hosted by Taylor and Francis Online.
In support of the restart of the Transient Reactor Test (TREAT) Facility at the Idaho National Laboratory, an analysis of a historic sodium loop experiment is performed. With the aging of the data and the beginning of a new campaign of transient testing, it is an ideal time to perform a modern analysis of a previously successful transient testing campaign. This work investigates many prior tests and ranks these tests for desirability of analysis using modern computational fluid dynamics (CFD) tools. Once the testing data were collected, necessary drawings were used to build a three-dimensional model of the test loop for CFD analysis. This geometry was then used to perform a multi-resolution analysis of the test loop. Three different resolution analyses were performed: a macroscale analysis detailing average flow characteristics in the test section using STAR-CCM+, a more refined analysis that investigated the thermal profile within the test section in more detail using STAR-CCM+, and a fine-mesh analysis that aims to lend credibility to the turbulence modeling performed in the lower-resolution analyses using Nek5000. The main goal was to show the feasibility of using modern computational tools for experiments performed at TREAT. With this analysis performed, a methodology has been outlined for future work to follow when analyzing the data from future TREAT tests. The more refined STAR-CCM+ analysis showed the best results when compared with data, showing that simulating the solid structures is an important feature of the analysis.