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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
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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. O. Slater, J. C. Robinson
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 332-337
Technical Note | doi.org/10.13182/NSE74-A23361
Articles are hosted by Taylor and Francis Online.
The solution of a special type of deep penetration problem is obtained by coupling a deep-penetration forward calculation with a localized adjoint calculation. The system on which the calculation is performed consists of a target far removed from a radiation source. In the absence of the target, the system geometry is simple (i.e., one- or two-dimensional). The problem is to compute some effect of interest (e.g., reaction rate, flux, etc.) within the target. The problem solution consists of (a) a source-centered calculation of the radiation field with the target absent, (b) a target-centered adjoint calculation on the system with the source absent, and (c) a coupling of the above two calculations. The technique has been applied to fissile and non-fissile targets located at various distances from and having various orientations with respect to a unit isotropic point fission neutron source in an infinite air medium.
