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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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May 2025
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.
Darius Lisowski, Alex Grannan, Matthew Jasica, SuJong Yoon, Florent Heidet
Nuclear Science and Engineering | Volume 196 | Number 1 | October 2022 | Pages S83-S97
Technical Paper | doi.org/10.1080/00295639.2022.2043540
Articles are hosted by Taylor and Francis Online.
To support the development of the U.S. Department of Energy (DOE) Versatile Test Reactor (VTR), a new set of experiments has been established at Argonne National Laboratory (ANL). Driven in part by the validation needs for code calculations and simulations of the reference VTR core design, three unique test facilities have been designed, or are in the process of being designed, to allow measurement of the phenomena and behavior prototypic to the full-scale VTR core. The Pressure drop Experimental Loop for Investigations of Core Assemblies in Nuclear reactors (PELICAN) facility, recently constructed and currently operational, is capable of producing full-scale flow rates for measurement of the pressure drop across a prototypic fuel assembly, including axial reflectors, fuel, and plenum components. The REDuced Scale Hydraulic Inlet Plenum (REDSHIP) experiment, beginning construction, will provide measurements of phenomena within the inlet plenum, including flow distributions through the core assembly ducts, pressure losses across the assembly receptacles, and localized velocity flow fields. A separate-effects-test experiment, called Parallel HEated ASsemblies for Advanced Nuclear Tests (PHEASANT), which is in the early stages of design, is being developed to examine the mixing of exiting core assembly jet streams within the upper plenum. As each of the test facilities becomes operational, they will begin generating timely, reliable, and qualified empirical data suitable for verification and validation of computational tools. In collaboration with other efforts across the DOE complex, the ANL experimental programs are well poised to provide continuous support for the advancement of the VTR design.
