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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
A. U. Rehman, D. G. Andrews
Nuclear Science and Engineering | Volume 52 | Number 3 | November 1973 | Pages 321-329
Technical Paper | doi.org/10.13182/NSE73-A19479
Articles are hosted by Taylor and Francis Online.
The thermalization of neutrons was experimentally measured for the purpose of testing Kushneriuk’s thermalization calculation in a cylindrical shell of moderator surrounding a fuel rod in a thermal reactor. The basis of this study was the measurement of activations for a set of five detectors—55Mn, 197Au, 115In, 239Pu, and 176Lu—inside the central fuel rod and the surrounding moderator at 20-cm hexagonal lattice pitch in the Atomic Energy of Canada Ltd.’s (AECL’s) heavy-water-moderated, natural uranium critical reactor, ZEEP. The neutron flux distribution, calculated by Kushneriuk’s method (first-order and exact solutions), was used in calculating detector activations. When compared, the measured detector activations and those calculated showed good agreement in the moderator, with the exception of points near and inside the fuel rod. The measured detector activations were also compared with the predicted values obtained from the HAMMER code. In this instance, the agreement was generally better than that obtained between measured and calculated values based on Kushneriuk’s method.
