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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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.
Kuldip Singh, C. C. St. Pierre
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 382-387
Technical Note | doi.org/10.13182/NSE73-A26573
Articles are hosted by Taylor and Francis Online.
Turbulent mixing rates between adjacent subchannels were obtained at 50 psia for annular flow of air-water mixtures in a simulated square-square rod bundle geometrical array using a tracer technique. The gap spacing was varied by a factor of 5. Mixing rates were found to be flow regime dependent, decreasing exponentially with subchannel mass flux and quality and increasing with gap spacing. Enhanced liquid interchange was measured in the low quality bubble flow regime and high quality annular flow regime. The results presented here are in qualitative agreement with data obtained by other investigators using steam-water at elevated pressures.
