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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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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.
O. E. Dwyer, H. C. Berry
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 284-303
Technical Paper | doi.org/10.13182/NSE71-A22362
Articles are hosted by Taylor and Francis Online.
The results of a theoretical study of molecular-conduction heat transfer to liquid metals flowing in-line through unbaffled rod bundles are reported. The flow is turbulent and fully developed, the heat transfer is fully developed, the bundles have equilateral triangular spacing, and there are no effects due to spacing devices. Circumferentially local heat transfer coefficients, rod-average heat transfer coefficients, and circumferential variation of wall temperatures have been obtained and correlated in terms of the various independent variables. The rods represent reactor fuel pins which consist of ceramic cores encased in metallic claddings. The following thermal boundary conditions were treated: (a) uniform wall heat flux in the axial direction and uniform wall temperature in the circumferential direction, on the outside surface of the cladding; (b) uniform wall heat flux in all directions on the outside surface of the cladding; and (c) uniform wall heat flux in all directions on the inside surface of the cladding. For boundary conditions (a) and (b), the independent variables are Reynolds number (Re) and rod spacing (P/D), while for boundary condition (c) there are two additional independent variables, i.e., relative cladding conductivity (kw/kf) and relative cladding thickness [(r2 - r1)/r2]. The results, all expressed in the form of convenient dimensionless groups, are presented in tables and charts and in the form of simple mathematical expressions for ready use by the design engineer.