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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
T. Asaoka
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 122-133
Technical Paper | doi.org/10.13182/NSE68-A19538
Articles are hosted by Taylor and Francis Online.
The jN method is applied within the context of a multigroup model to solve neutron transport problems for an infinite homogeneous slab with finite thickness under the assumption that the scattering of neutrons is spherically symmetric in the laboratory system. Stationary space-angle energy-dependent problems are treated as a special case of time-dependent problems. The numerical results for the vector flux generated by a stationary boundary source show that the j5 approximation gives an accuracy comparable to the S8 approximation in Carlson's theory, regardless of the size of the system. The transient time behavior of leakage neutrons is calculated on the basis of a one-group model and compared with Monte Carlo results. The j7 approximation gives values which agree well with those of the Monte Carlo calculation. In addition, the leakage neutron fluxes from copper blocks are obtained by the use of a 7 group j7 approximation as a function of time and the decay constants are compared with the experimentally observed values.
