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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
J. T. Mihalczo
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 489-504
Technical Paper | doi.org/10.13182/NSE72-A22568
Articles are hosted by Taylor and Francis Online.
Cylinders and cylindrical annuli of uranium metal (93.15 wt% 235U), with diameters varying from 7 to 15 in., were assembled to delayed criticality with graphite reflectors varying in thickness up to 18 in. or with an effectively infinite thickness polyethylene on all outer surfaces. In one series of measurements a polyethylene reflector was also placed adjacent to only one flat surface of the cylinders. The multiplication factor calculated by both Sn transport and Monte Carlo methods, with various sets of cross sections agreed very well with the experimental values. As a result of the high order of Sn and the large number of spatial intervals required, the computing time for the transport theory calculations was a factor of 10 larger than that required for the Monte Carlo calculations with standard deviations of 1%.
