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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
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.
