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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
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.
G. I. Coulbourn, T. G. Williamson
Nuclear Science and Engineering | Volume 35 | Number 3 | March 1969 | Pages 376-383
Technical Paper | doi.org/10.13182/NSE69-A20017
Articles are hosted by Taylor and Francis Online.
The fast-neutron spectrum and dose rate were measured at various distances from a point fission-neutron source in water and in two aluminum and water mixtures using seven threshold reaction detectors and p-i-n silicon diode dosimeters. The experimental results were compared with calculations made using the ANISN computer code. The threshold reactions used were the 115In(n, n′), 32S(n, þ), 64Zn(n, þ), 27Al(n, þ), 56Fe(n, þ), 24Mg(n, þ), and 27Al(n, α). Using experimentally determined counting efficiencies, absolute saturation activities of the threshold reaction products were determined. A method of neutron-spectrum unfolding was devised which represented the fast-neutron spectrum by a group of successive exponentials, calculated from the saturation activities. The reported spectra generally agreed well with the results predicted by the ANISN code. The fast-neutron dose rate was measured directly using p-i-n junction dosimeters and indirectly by applying flux-to-dose conversion factors to the measured fast-neutron flux. Good agreement was obtained between these measurements and calculations