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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.
S. Shalev, J. M. Cuttler
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 52-66
Technical Paper | doi.org/10.13182/NSE73-A23257
Articles are hosted by Taylor and Francis Online.
A high-pressure 3He proportional counter has been developed with good energy resolution for fast neutrons, and detailed descriptions are given of its construction and calibration and the determination of its response function. The spectrometer was used to measure the delayed-neutron energy distribution for samples of 232Th, 233U, 235U, 238U, and 239Pu repetitively irradiated in the Israel Research Reactor-1. Irradiation and counting times were optimized to accentuate group 2 and group 4 delayed neutrons. Corrections were applied for the finite energy resolution, for the energy-dependent detection efficiency and for spectrum distortion due to gamma rays. An approximate energy spectrum was obtained for group-1 delayed neutrons, and more precise spectra were obtained for group-2 delayed neutrons from each of the samples investigated. Preliminary results are also given for group-4 delayed neutrons from 232 Th and 235 U.
