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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
U. Hansen, R. Schulten, E. Teuchert
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 132-139
Technical paper | doi.org/10.13182/NSE72-A28426
Articles are hosted by Taylor and Francis Online.
A new and promising operating modus for the pebble-bed reactor has been investigated. Instead of circulating the fuel balls several times through the core they are moved only once slowly from the top to the bottom. Due to the increasing depletion toward the lower core area, there is a substantial axial tilt of the power density, and the downward flow of the cooling gas ensures for the system an optimal heat removal. The reduced power generation in the hot core area and the absence of hot spots enable achievement of a higher power density than in the known pebble-bed type and make possible a rise in the average gas outlet temperature up to 950°C. For a UO2-fueled reactor the life history is followed for several years by means of a two-dimensional calculational approach. Apart from the advantages in thermodynamics, the new system is marked by a very short and smooth running-in period, by a high sensibility of reactivity to control poison changes inside the upper reflector, and by an ideal accommodation of the burnup in the balls running with different flow speeds in different radial positions. The spatial distribution of the power density can be flexibly manipulated by changes in the fuel cycle speed, in fuel ball layout, or by the use of a higher feed enrichment in the outer core region. A brief parameter study and a discussion of technological aspects give an outline of the developing potential of that new type.