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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.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Latest News
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
C. R. Bell, N. P. Oberle, W. Rohsenow, N. Todreas, C. Tso
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 458-465
Technical Paper | doi.org/10.13182/NSE74-A23376
Articles are hosted by Taylor and Francis Online.
A series of studies was made of bubble nucleation by fission fragments and fast neutrons. The experimental work was conducted by a liquid suspension method in a pressure chamber designed to provide for visual determination of the onset of nucleation. The minimum superheat necessary for nucleation of visible bubbles was measured in water and propylene glycol. An analytic prediction method for the superheat threshold is presented, utilizing the “thermal spike” theory of Seitz and Rayleigh’s criteria for instability of a vapor jet in liquid. This method predicts that the important parameter a, equal to the ratio of the track length in which net energy must be deposited to the critical bubble radius, should equal 6.07. By this analysis, this value is independent of the type of thermal-spike-producing radiation, the type of fluid, and the system condition. The experimental data from this investigation and all other published data were examined to determine the applicable a values. This examination did not result in identification of a values consistent with the proposed prediction. Reasons for the deviation of the data from predictions are discussed, but the basis of the deviations cannot be resolved.