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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.
W. Jaschik, L W. Seifritz
Nuclear Science and Engineering | Volume 53 | Number 1 | January 1974 | Pages 61-78
Technical Paper | doi.org/10.13182/NSE74-A23330
Articles are hosted by Taylor and Francis Online.
A sophisticated model is presented for the calculation of prompt-response self-powered neutron (SPN) detectors used for stationary as well as nonstationary neutron flux measurements in nuclear reactor cores. The technique recommended for calculating the unit sensitivity in terms of A/(cm) per unit flux takes the following into account:, neutron self-shielding factor of the emitter, flux depression correction, Compton and photoelectron production rate due to self-absorption of the gamma-ray cascade emitted immediately after neutron capture, electron escape probability from the emitterm, loss of electron energy within the emitter, range of the electrons in the insulator which contains a space-charge electric field., Calculated thermal and fast unit sensitivities in a typical light-water-reactor neutron spectrum for four potential prompt-response SPN detectors, whose emitters consist of cobalt, cadmium, erbium, and hafnium, are compared with experimental data and are found to be in satisfactory agreement.