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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
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