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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
M. Necati Özişik, Daniel Hughes
Nuclear Science and Engineering | Volume 35 | Number 3 | March 1969 | Pages 384-393
Technical Paper | doi.org/10.13182/NSE69-A20018
Articles are hosted by Taylor and Francis Online.
The steady-state flux of matter of molecular size from a mixture of vapor and noncondensable gas to the walls of a large containment vessel during the condensation of vapor can be predicted with the present analysis. A boundary layer approach has been used in formulating the mass-transfer problem and the resulting equations are solved numerically. Charts are presented for the flux of molecular iodine from a steam-air mixture to the walls of the containment vessel during the condensation of steam. Knowing the total pressure and the temperature of the bulk mixture, the wall temperature, and the concentration of air and iodine in the bulk mixture, the rate of removal of iodine from the vessel can be predicted. The analysis is correlated with an experiment and close agreement is found.