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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
J. B. Rivard
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 344-349
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32337
Articles are hosted by Taylor and Francis Online.
First-of-a-kind fission-heated experiments utilizing uranium oxide particles in liquid sodium have been performed to assess the nature of the passive heat transfer between fast reactor fuel debris and overlying coolant. The experiments were designed to simulate the situation following a core disruptive accident in which molten core material is quenched, fragmented, and is dispersed as beds of decay-heated particulate within the reactor vessel. In two of the experiments, threshold dryout of the fuel particulate was produced. During several runs, dryout was maintained for long periods (∼1 h) with only modest temperature increases, demonstrating that while bed dryout may be a necessary condition for remelting of the fuel, it is not always a sufficient condition.