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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
W. F. Miller, Jr., E. E. Lewis, E. C. Rossow
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 148-156
Technical Paper | doi.org/10.13182/NSE73-A26590
Articles are hosted by Taylor and Francis Online.
The finite element method is applied to the one-dimensional neutron transport equation. Piecewise bilinear or trilinear polynomials that are continuous in the space-angle phase space are utilized in an even-parity functional for the angular flux to establish linear simultaneous sets of algebraic equations. Both inhomo-geneous and eigenvalue problems in slab, spherical, and cylindrical geometries are treated. The application of the finite element method to problems with anisotropic scattering and material interfaces is also demonstrated. In all cases, the accuracy of the finite element results is an improvement over that obtained from standard SN calculations using comparable numbers of simultaneous equations.
