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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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March 2025
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Fusion Science and Technology
February 2025
Latest News
WEST claims latest plasma confinement record
The French magnetic confinement fusion tokamak known as WEST maintained a plasma in February for more than 22 minutes—1,337 seconds, to be precise—and “smashed” the previous record plasma duration for a tokamak with a 25 percent improvement, according to the CEA, which operates the machine. The previous 1,006-second record was set by China’s EAST just a few weeks prior. Records are made to be broken, but this rapid progress illustrates a collective, global increase in plasma confinement expertise, aided by tungsten in key components.
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.