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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
NuScale Energy Exploration Center opens at SC State
NuScale Power Corporation’s latest Energy Exploration (E2) Center has opened at South Carolina State University, in Orangeburg. E2 Centers are designed to provide visitors with hands-on experiences in simulated scenarios of operations at nuclear power plants. NuScale has established 10 such centers around the world. The company officially presented the fully installed E2 Center to SC State on May 21, after a collaborative setup and training process was completed.
F. C. Engel, R. A. Markley, A. A. Bishop
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 290-296
Technical Paper | doi.org/10.13182/NSE79-A20618
Articles are hosted by Taylor and Francis Online.
Laminar, transition, and turbulent parallel flow pressure drop across wire-wrapped hexagonal rod bundles positioned inside a duct were determined in tests using water, sodium, and air. A smooth transition region from turbulent to laminar flow that occurred over the Reynolds number range from 5000 to 400 characterized the resulting friction factor behavior. The continuous transition region could be explained in terms of the fraction of the flow area in turbulent flow. Laminar friction factors calculated from individual subchannel measurements could be correlated by the same expression found for rod-bundle-averaged conditions. In the laminar range, the friction factor was correlated by the expression f = 110/Re, in the turbulent range by f = 0.55/Re0,25, and in the transition range by where is the intermittency factor. A general laminar flow friction factor correlation was developed: This correlation agrees satisfactorily with limited laminar flow data from rod bundles having different wire-wrap lead pitch-to-diameter ratios.