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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.
Keith E. Asmussen, Paul Wälti
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 359-365
Technical Paper | Reactor | doi.org/10.13182/NT72-A16033
Articles are hosted by Taylor and Francis Online.
The plutonium loadings were determined for a test element for irradiation in the Peach Bottom HTGR. The test element is a graphite circular cylinder with an array of eight fuel rods in a circular pattern. The fuel rods contain dense spherical kernels of PuO2 or PuO2/3 ThO2. Be cause of the strong Pu resonances, the heterogeneity effects in the test element are strongly marked. A code for treating this rather complicated problem rigorously was not available. Thus the problem was simulated within a onedimensional transport code by equating three collision probabilities. The heterogeneities were seen to result in significant grain selfshielding, rod selfshielding, and mutual shielding of the rods. The Pu loading for the central fuel body of the test element was determined to be 19.0 g.