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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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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.
Li-Chi Cliff Po
Nuclear Science and Engineering | Volume 98 | Number 2 | February 1988 | Pages 154-161
Technical Paper | doi.org/10.13182/NSE88-A28495
Articles are hosted by Taylor and Francis Online.
The once-through steam generator version of the personal computer transient analyzer, PCTRAN/P, was used to simulate the overcooling event that occurred on December 26, 1985, at Rancho Seco. Loss of power to the integrated control system led to a reactor trip and overfeeding by the auxiliary feedwater with excessive steam dump. As a result, the plant cooled down rapidly in a short period. PCTRAN/P has successfully reproduced the transient using its interactive control functions. Areas of the system’s design deficiencies are thus identified and modifications can be made to prevent a similar event from recurring. The computation time on an IBM-PC/XT was ∼20 min for the 50-min transient. This demonstrates that PCTRAN/P can be used as a fast-turnaround tool for conducting reactor transient analyses.