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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.
Man Gyun Na, Won Il Ko, Hangbok Choi
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 315-326
Technical Paper | doi.org/10.13182/NSE02-A2310
Articles are hosted by Taylor and Francis Online.
A combination method of spent pressurized water reactor (PWR) fuel is proposed that adjusts the fuel composition for direct use of spent PWR fuel in Canada deuterium uranium (CANDU) reactors (DUPIC). This method reduces the composition heterogeneity (variation) of the DUPIC fuel caused by directly reusing spent PWR fuel as DUPIC fuel feedstock. In this study, a combination method was used to find the optimum mixture composition from the spent PWR fuel database by minimizing the composition variation of the major fissile isotopes 235U and 239Pu. The simulation results have shown that the combination method can reduce the composition variation of 235U and 239Pu to 0.11 and 1.40%, respectively, through assemblywise mixing operation only. It is also believed that the result could be improved further through a rodwise combination technique if the isotopic composition of each spent PWR fuel rod is known by direct measurement during the DUPIC fuel fabrication process.
