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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.
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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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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.
Vito Renda, Loris Papa
Fusion Science and Technology | Volume 20 | Number 1 | August 1991 | Pages 40-47
Technical Paper | Divertor System | doi.org/10.13182/FST91-A29641
Articles are hosted by Taylor and Francis Online.
The performance and limits of a divertor plate for the Next European Torus (NET) are assessed. The design is a plasma-facing component that integrates the divertor plates and the inboard first wall in a monoblock panel. It is made of stainless steel poloidal U-tubes embedded in a copper matrix and protected by a carbon-fiber composite graphite armor. The thermal and thermomechanical behavior are analyzed in the high thermal flux zone taking into account the actual surface heating, which ranges from 5 to 10 MW/m2. A simplified preliminary analysis assesses the water flow and the component geometry in accordance with the system and material data foreseen for NET. It is shown that if the surface temperature of the armor is limited to 1273 K, the graphite thickness must be limited to 7.5 mm. Detailed thermal and mechanical finite element analyses, performed by the CASTEM 2000 code, show that the cooling tubes remain just below the creep regime temperature. The allowable limits prescribed by international standards are met, and the component's lifetime is 3000 cycles.