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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Daniel López, Javier Sanz, Francisco Ogando
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 252-257
IFMIF | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14143
Articles are hosted by Taylor and Francis Online.
During the IFMIF/EVEDA phase, a 125 mA and 9 MeV deuteron prototype accelerator will be designed and tested for the final IFMIF project. Deuteron losses will occur during operation of the accelerator at several components as well as at the beam stopping, leading to material activation induced by deuterons and/or by secondary neutrons, depending on the location. This work is focused on the residual dose rate assessment inside the accelerator vault due to the radioactive inventory induced in the main accelerator components, the outside concrete structures of the accelerator vault, and the concrete-made local shielding of the beam dump. The results will be useful for maintenance work planning, identifying hot areas in the accelerator region. The adopted computational procedure uses MCUNED for determination of spatial distribution of deuteron and neutron fluxes, ACAB for activation calculations, and MCNPX for transport of decay gammas. Deuteron transport cross sections are taken from TENDL-2010 and decay and activation cross-section data from EAF-2007.