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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.
