ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
D. M. France, R. D. Carlson, R. R. Rohde, G. T. Charmoli
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE74-A23959
Articles are hosted by Taylor and Francis Online.
Sodium voiding during the initial time period subsequent to boiling inception was studied experimentally under forced convection with system parameters typical of liquid-metal fast breeder reactors. The annular flow area of the test section simulated a single reactor fuel element of 3-ft heated length. Transient void formations were measured along the test section length. Initial sodium-voiding characteristics were related to the maximum bulk superheat existing in the test section at the time of boiling inception. Significant differences in test section voiding were obtained under conditions of zero and high (100 to 160°F) superheats. Loop and pot-type reactor simulation conditions were employed.