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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.
C. S. Barnett
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 398-401
Technical Note | doi.org/10.13182/NSE73-A26578
Articles are hosted by Taylor and Francis Online.
Consider one-speed model neutron migration in an infinite homogeneous medium. Let a neutron be released from the origin at time zero. A probabilistic argument is used to show that without approximation the neutron’s mean square distance from the origin at time t, given that absorption has not occurred, is , where v is the neutron speed, λs is the scattering mean-free-path, and is the mean cosine of the scattering angle. The expression outside the brace is the diffusion theory result. For large t, the exact result tends to the diffusion theory result, while for small t, the exact result tends to (vt)2, an extreme nondiffusion result.