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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
DOE issues RFI for a spent fuel consolidated interim storage facility
The Department of Energy’s Office of Nuclear Energy has issued a request for information opportunity for the design and construction of a federal consolidated interim storage facility (CISF) for spent nuclear fuel. The DOE is planning on establishing a federal CISF to manage SNF until a permanent repository is available. In May, the DOE received initial approval, known as “Critical Decision-0,” for such a facility.
The deadline for submissions is September 5.
L. Crosatti, J. B. Weathers, D. L. Sadowski, S. I. Abdel-Khalik, M. Yoda, R. Kruessmann, P. Norajitra
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 70-74
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-30
Articles are hosted by Taylor and Francis Online.
A modular helium-cooled divertor design based on the multi-jet impingement cooling concept, known as the helium-cooled multi-jet (HEMJ), has been developed at the Karlsruhe Research Center (FZK). Thermal-hydraulic design simulations have shown that the HEMJ divertor can accommodate an incident heat flux of at least 10 MW/m2 with local heat transfer coefficients as high as ~50 kW/(m2K). However, there were no experimental data to validate the calculated thermal performance. An experimental study of the HEMJ divertor was therefore performed at Georgia Tech in collaboration with FZK. An experimental test module duplicating the prototypical HEMJ geometry and material properties was designed, fabricated, instrumented, and tested in an air flow loop at different incident heat flux values. The air flow rate was selected to cover a wide range of Reynolds numbers spanning that for the actual HEMJ, namely 2.1 × 104. The measured temperature distributions and local heat transfer coefficients estimated from these temperature distributions are both in good agreement with numerical predictions of the air-cooled test module performance calculated using FLUENT[registered] 6.2 for all test conditions. This research supports earlier numerical predictions of the thermal performance of the HEMJ design, and provides added confidence in the ability of the FLUENT[registered]CFD package to accurately predict the thermal performance of various gas-cooled plasma-facing components with complex geometry.