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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
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.