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
October 2025
Fusion Science and Technology
Latest News
Hot Fuel Examination Facility named a Nuclear Historic Landmark
The American Nuclear Society recently announced the designation of three new nuclear historic landmarks: the Hot Fuel Examination Facility (HFEF), the Neely Nuclear Research Center, and the Oak Ridge Gaseous Diffusion Plant. Today’s article, the first in a three-part series, will focus on the historical significance of HFEF.
Timothy D. Welch, August W. Cronenberg
Nuclear Science and Engineering | Volume 67 | Number 2 | August 1978 | Pages 263-269
Technical Note | doi.org/10.13182/NSE78-A15444
Articles are hosted by Taylor and Francis Online.
An important question to the liquid-metal fast breeder reactor safety program is a description of molten fuel dynamics, or, more specifically, whether fuel will freeze locally on structural material within the reactor core, preventing dispersal and nuclear shutdown, or in the extremeties of the fuel assembly. In this Note, a comparison is made between the solidification processes for single-component (i.e., UO2) and mixed-oxide fuel [i.e., (U, Pu)O2] by solving a Stefan-type problem for both pure and binary alloy solidification. Analytic calculations indicate that the freezing rate of the mixed fuel is not significantly different from that for the single-component system; thus, single-front analysis may be used for such mixed-oxide fuels in assessing safety questions associated with solidifacation phenomena.