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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Peter Jansson, Martin Bengtsson, Ulrika Bäckström, Francisco Álvarez-Velarde, Dušan Čalič, Stefano Caruso, Ron Dagan, Luca Fiorito, Lydie Giot, Kevin Govers, Augusto Hernandez Solis, Volker Hannstein, Germina Ilas, Marjan Kromar, Jaakko Leppänen, Marita Mosconi, Pedro Ortego, Rita Plukienė, Arturas Plukis, Anssu Ranta-Aho, Dimitri Rochman, Linus Ros, Shunsuke Sato, Peter Schillebeeckx, Ahmed Shama, Teodosi Simeonov, Alexey Stankovskiy, Holly Trellue, Stefano Vaccaro, Vanessa Vallet, Marc Verwerft, Gašper Žerovnik, Anders Sjöland
Nuclear Science and Engineering | Volume 196 | Number 9 | September 2022 | Pages 1125-1145
Technical Paper | doi.org/10.1080/00295639.2022.2053489
Articles are hosted by Taylor and Francis Online.
The decay heat rate of five spent nuclear fuel assemblies of the pressurized water reactor type were measured by calorimetry at the interim storage for spent nuclear fuel in Sweden. Calculations of the decay heat rate of the five assemblies were performed by 20 organizations using different codes and nuclear data libraries resulting in 31 results for each assembly, spanning most of the current state-of-the-art practice. The calculations were based on a selected subset of information, such as reactor operating history and fuel assembly properties. The relative difference between the measured and average calculated decay heat rate ranged from 0.6% to 3.3% for the five assemblies. The standard deviation of these relative differences ranged from 1.9% to 2.4%.