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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
J. Hoover, G. K. Leaf, D. A. Meneley, P. M. Walker
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 52-65
Technical Paper | doi.org/10.13182/NSE71-1
Articles are hosted by Taylor and Francis Online.
A fuel cycle analysis system is presented for performing fast reactor fuel cycle calculations. The REBUS system, an acronym for REactor BUrnup System, solves for the infinite time (equilibrium) operating conditions of a recycle system under fixed conditions. REBUS obtains the feed enrichments, the burn step (operating) time, and the control requirements which satisfy the constraint on the fuel discharge burnup, give the desired unpoisoned multiplication constant at some specified time during reactor operation, and maintain criticality. REBUS includes models of both the in-reactor fuel management and the external cycle. The in-reactor fuel management model permits any physically realizable fuel management scheme. In the external cycle, reprocessing and sale of the discharged fuel and refabrication with charge fuel makeup from reprocessing plants and/or external feed supplies can be studied. The isotope chain matrix may contain β−, β+, and α-decay terms as well as (n, γ), (n, p), (n, α), (n, 2n), and (n, f) reactions. The REBUS system is comprised of a neutronics model and a fuel cycle model. The fuel cycle model contains no geometric information so that any neutronics solution can be used (zero to three dimensional, diffusion or transport theory, direct or synthesis). REBUS has been operated with one- and two-dimensional diffusion theory neutronics models up to the present time.