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.
Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
Prepare for the 2025 Nuclear PE Exam with ANS guides
The next opportunity to earn professional engineer (PE) licensure in nuclear engineering is this fall, and now is the time to sign up and begin studying with the help of materials like the online module program offered by the American Nuclear Society.
S. W. Hong, Y. S. Na, S. H. Hong, J. H. Song
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 538-552
Technical Paper | doi.org/10.13182/NT16-9
Articles are hosted by Taylor and Francis Online.
Some advanced reactors adapt the in-vessel corium retention concept by cooing the outside wall of the reactor vessel in severe accidents. If a reactor vessel failure happens in this case, the molten corium in the reactor vessel is directly injected into the water in the reactor cavity without the process of a free fall. Experiments using ZrO2 and molten corium to simulate the conditions in which the reactor vessel is fully flooded were recently carried out at the Test for Real cOrium Interaction with water (TROI) experimental facility, and the results are compared with the data produced under conditions in which the reactor vessel is partially flooded. It was observed that the melt front velocity in the water under submerged reactor conditions is much faster than that under partially flooded reactor cavity conditions, and a large bubble was observed at the surface of the mixing zone under submerged reactor conditions. Accordingly, it is estimated that the breakup of the melt jet in the water during the fuel-coolant interaction (FCI) test under submerged reactor conditions would be different than that of the FCI test under partially flooded reactor cavity conditions.