ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
S. Yeom, J. Eoh, J. Hong, J.-Y. Jeong
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 338-345
Technical Paper | doi.org/10.13182/NT16-30
Articles are hosted by Taylor and Francis Online.
The Sodium Test Loop for Safety Simulation and Assessment (STELLA) program for demonstration of decay heat removal performance of the Prototype Generation-IV Sodium-cooled Fast Reactor (PGSFR) is in progress at Korea Atomic Energy Research Institute. As the first phase of the program, the STELLA-1 facility has been constructed, and separate-effect tests for the sodium heat exchangers of the safety-grade passive decay heat removal system (PDHRS) have been conducted. A natural-draft sodium-to-air heat exchanger, one of the key heat exchangers of PDHRS, was tested for the performance demonstration and the design code verification and validation. Twenty-nine cases of experiments were conducted with 13 different test conditions for the selected operating and design conditions of PGSFR. Heat transfer rates were experimentally estimated based on the measured inlet/outlet temperatures and flow rates of both the shell side and the tube side. The experimentally obtained heat transfer rates were compared with the values calculated from the design code, which showed good agreement within a 12.6% error range. Finally, the average Nusselt number was obtained from the experimental results considering the convection mode.