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Division Spotlight
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.
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.
Chia-Jung Hsu
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 380-388
Technical Note | doi.org/10.13182/NSE72-A22426
Articles are hosted by Taylor and Francis Online.
The heat transfer characteristics of a rod which is dislocated from its symmetrical position are studied analytically for slug flow through tightly packed rod bundles (P/D ratio down to ≈1.00). Explicit equations describing the temperature fields in the fuel core, the cladding, and the elemental coolant flow area are obtained by assuming uniform fuel power density. Variation of the rod-average Nusselt number, as well as the heat flux distribution at the outer wall of the cladding, is examined for selected values of σ, the P/D ratio, the cladding thickness parameter, λ(=r1/r2) and the thermal conductivity ratios, κ and κw. The present solutions, when specialized to the case of σ = 0.0 (i.e., no rod displacement) show excellent agreement with the results reported by Axford and by Dwyer and Berry who studied the corresponding three-region and two-region problems, respectively, for symmetrical rod bundles with no rod displacement.
