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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.
D. V. Gopinath, K. Santhanam, D. P. Burte
Nuclear Science and Engineering | Volume 52 | Number 4 | December 1973 | Pages 494-498
Technical Note | doi.org/10.13182/NSE73-A23320
Articles are hosted by Taylor and Francis Online.
The Anisotropic Source-Flux Iteration Technique (ASFIT) is a semianalytical method based on collision probabilities for energy-dependent radiation transport. In its original form, the coupled integral equations for space and energy-angle transmission were solved using discrete ordinate representation in space and energy and polynomial approximation in direction cosine for radiation flux and source terms. In this Note, the following modifications of ASFIT are presented: 1. discrete ordinate representation in direction cosine 2. sequential integration in space 3. exponential transformation in space 4. multiple energy structure for neutron transport. The Note discusses the rationale for these modifications, and their effect on the speed of computation, convergence, and capabilities of the code.
