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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
F. C. Difilippo, N. B. Pieroni, J. C. Viez
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 262-271
Technical Paper | doi.org/10.13182/NSE73-A26604
Articles are hosted by Taylor and Francis Online.
Through the measurement of the kinetic distortion effect, defined as the modal shape and spectral difference between the fundamental prompt- and delayed-neutron modes, a spatial correction factor for the reactivity of the system, as determined by the Gozani and Garelis-Russell modified pulsed-source methods, is obtained. This factor is the ratio of the experimentally determined and properly normalized delayed- and prompt-neutron densities measured in a pulsed-neutron experiment. With this spatial correction factor the reactivity of the system is obtained as a true global parameter. The results of measurements in several 235U enriched-uranium cores reflected by light water and by graphite and light water are presented.