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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.
Hans G. Kaper, Gary K. Leaf, Arthur J. Lindeman
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 27-48
Technical Paper | doi.org/10.13182/NSE72-A22525
Articles are hosted by Taylor and Francis Online.
This paper contains the results of detailed comparison studies of the efficiency of high order finite element approximations vs low order finite difference approximations, for the numerical solution of the static multigroup diffusion equation in two dimensions. The comparisons are based on the execution times for a Keff calculation with a prescribed precision for two particular computer programs— HOD (finite elements) and D ARC2D (finite differences). The calculations were performed for three different types of reactor configurations: a simple two-zone configuration with two energy groups, a multizone configuration [1000-MW(e) LMFBR mockup] with four energy groups, and a loosely coupled configuration with two energy groups. The conclusions are: 1. The use of high order approximation procedures based on finite element methods leads to substantial execution time savings and offers not just a viable alternative to the use of low order approximation procedures based on finite difference methods; it is, indeed, a significant advancement in computational capability. 2. With high order approximation procedures based on finite element methods it is possible to obtain, at reasonable cost, solutions to the multigroup diffusion equation which are sufficiently accurate that any errors can be attributed to either the diffusion theory approximation or other approximations in the reactor model, rather than to the numerical approximation procedure. 3. Solutions obtained with the finite element method provide as much accuracy in the flux inventories as in the multiplication factor.
