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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Thomas Moore, Mike Steer, Marco Delchini, Mathieu Martin, Brian Woods
Nuclear Technology | Volume 206 | Number 6 | June 2020 | Pages 862-894
Technical Paper | dx.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.