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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Robert E. Henry, Hans K. Fauske, Stuart T. McComas
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 79-91
Technical Paper | doi.org/10.13182/NSE70-A20366
Articles are hosted by Taylor and Francis Online.
Steam-water, two-phase critical flows were obtained in long pipes (L/D > 40) for mass flow rates ranging from 512 to 6460 lbm/(sec ft2), exit pressures from 40 to 150 psia, and thermodynamic equilibrium qualities from 0.0019 to 0.216. A comparison of the three test sections employed indicates that previous experimental data are in error for qualities less than 0.10 due to the influence of the downstream two-dimensional expansion on wall pressure taps located near the exit plane. Although simultaneous temperature and pressure measurements were not taken, the data exhibit trends that suggest the existence of a nonequlibrium phase change. Experimentally determined exit and axial void fractions indicate (a) that the velocity ratios are considerably less than the existing analytical predictions and (b) that previously dissolved gases existing from the liquid provide a source for vapor formation under adiabatic subcooled conditions.