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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
Hans Ludewig
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 398-405
Technical Paper | doi.org/10.13182/NSE71-A20170
Articles are hosted by Taylor and Francis Online.
An analysis of the BNL heterogeneity experiment is described in this paper. The nuclear data used are based on ENDF/B Versions I and II and the DSN method is used in the analysis. In addition to determining the intracell fine structure for 235U and 238U fission and Mn capture, the variation of absolute 235U/238U fission ratio as a function of cell size is investigated. From these results it can be concluded that the fission ratio calculations are particularly sensitive to the fission cross section of 235U and 238U, suggesting that measurements of this type could be useful in checking the accuracy of data. The overall agreement between computed and measured quantities was found to be good for all quantities that could be characterized as asymptotic. The non-asymptotic nature of some quantities is investigated using two-dimensional calculations.
