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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.
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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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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.
R. A. Rydin, J. A. Burke, W. E. Moore, K. W. Seemann
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 179-196
Technical Paper | doi.org/10.13182/NSE71-A22352
Articles are hosted by Taylor and Francis Online.
A series of space-time reactor kinetics experiments has been performed in the Solid Homogeneous Assembly. The ground rules were the following: 1. The cores were to be easy to model statically using few-group diffusion theory. 2. The dynamic behavior was to be one dimensional. 3. Significant flux tilt and delayed neutron flux tilt holdback effects were to be present. 4. The perturbation was to be essentially a negative step change in reactivity. 5. The flux distributions, absorber worths, and eigenvalue separation of each core were to be measurable in order to use this information to verify the core modeling process. The adequacy of few-group diffusion theory was checked using both one-dimen-sional multigroup (fast and thermal) and two-dimensional few-group transport theory calculations. The few-group diffusion theory model was solved in a cylindrical approximation using a finite difference code, and in correct 3D geometry using a synthesis code; the latter did an excellent job of predicting criticality and matching foil activation traverses made using the 55Mn (n, γ) thermal and 115In (n, n’) threshold reactions. The eigenvalue separation of each core was measured using both a static flux tilt method and a two-detector noise correlation method; the results agreed well with calculated values, indicating that these new experimental methods can provide an accurate determination of the eigenvalue separation of a core. The transient response of one of the cores to a step perturbation was compared to the response calculated using the space-time synthesis model. In general, it has been found that the transient response of the core can be predicted accurately provided that the core is well modeled statically, including the perturbation worth and the eigenvalue separation, and provided that the effective delayed neutron fraction is properly evaluated. This tends to verify the adequacy of existing methods for computing spatially dependent transients in cores describable by few-group diffusion theory.