ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.