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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
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.