ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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!
Latest Magazine Issues
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
Chang H. Oh, Goon C. Park, Cliff Davis
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 107-117
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8855
Articles are hosted by Taylor and Francis Online.
An air-cooled helical coil reactor cavity cooling system (RCCS) unit immersed in the water pool was proposed to overcome the disadvantages of the weak cooling ability of an air-cooled RCCS and the complex structure of a water-cooled RCCS for the high-temperature gas-cooled reactor (HTGR). An experimental apparatus was constructed to investigate the various heat transfer phenomena in the water pool-type RCCS, such as the natural convection of air inside the cavity, radiation in the cavity, the natural convection of water in the water pool, and the forced convection of air in the cooling pipe.The RCCS experimental results were compared with published correlations. The CFX code was validated using data from the air-cooled portion of the RCCS. The RELAP5 code was validated using measured temperatures from the reactor vessel and cavity walls.