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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
Salman M. Alshehri (Missouri S&T/KACST), Ibrahim A. Said (Alexandria Univ/Rice Univ), Muthanna H. Al-Dahhan (Missouri S&T/KACST/Alexandria Univ/Rice Univ), Shoaib Usman (Missouri S&T)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 670-681
Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri S&T has designed, developed, and tested a dual channel module. The facility represents a scaled down prismatic modular reactor to mimic pressurized conduction cooldown (PCC) accident scenario for the prismatic modular reactor with a reference to High-Temperature Test Facility at Oregon State University (OSU-HTTF). The current facility was constructed to investigate a plenum-to-plenum (P2P) natural circulation heat transfer through two channels for different coolants (working fluid) at high operating pressure of 413.7 kPa. The natural circulation heat transfer in terms of temperature fields and heat transfer coefficients across the core of current facility (i.e., channels) has been investigated at constant outer surface temperature of upper plenum and downcomer channel (278.15 K) under nonuniform heating center peaking step (approximating cosine shape) using an advanced fast response heat transfer technique. Results showed that a net inner surface temperature gain along the riser channel by 84, 95, 98 and 150K for carbon dioxide, nitrogen, argon, and helium respectively. Also, an average increasing of centerline temperature along the riser channel is observed by 110, 133, 151 and 204 K for carbon dioxide, nitrogen, argon and helium, respectively. Furthermore, the current results show a common heat transfer coefficients trend for all coolants along the riser channel; the local heat transfer coefficient decrease with axial location from the entrance (Z/L = 0.044) until a minimum value at Z/L = 0.279 and after this position, the local heat transfer coefficient starts to increase again till Z/L= 0.591 (laminarization effects). And finally, heat transfer coefficient decrease from Z/L= 0.591 till the exit into the upper plenum. However, it was observed that heat transfer coefficients for helium was higher than all other gases for the entire riser channel and remained positive for much higher heights. In the laminarization effects region (0.279