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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.
Gary S. Hoovler, M. Neil Baldwin, Ray L. Eng, Fred G. Welfare
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 217-237
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel | doi.org/10.13182/NT80-A32604
Articles are hosted by Taylor and Francis Online.
Close-packed storage of light water reactor (LWR) fuel assemblies is needed to expand the capacity of existing underwater storage pools. This increased capacity is required to store the large volume of spent fuel that arises from prolonged on-site storage. To provide benchmark criticality data in support of this effort, an experimental program sponsored by the U.S. Department of Energy was undertaken. Low-enriched UO2 fuel pins in a water-moderated lattice were used to construct 20 critical assemblies that simulated a variety of close-packed LWR fuel storage configurations. The critical assemblies consisted of nine LWR-type fuel assemblies (clusters) grouped in a radially reflected 3×3 array. Both the spacing and material between the fuel clusters were varied to provide numerous critical configurations. All pertinent data for each critical assembly are documented in sufficient detail to validate calculational methods according to the American National Standards Institute standard N16.9-1975. Criticality calculations using the Monte Carlo code KENO IV were performed for comparison with the experimental data. The comparison shows that the calculational model underestimates keff when separation between fuel clusters is >1 pin pitch (1.64 cm), and that the degree of underestimation increases as the spacing widens.