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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
V. Widak, P. Norajitra, J. Reiser
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 1028-1032
Divertors and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9046
Articles are hosted by Taylor and Francis Online.
Within the EU power plant conceptual study (PPCS), a modular He-cooled divertor concept (Ref. 1) has been investigated at the Forschungszentrum Karlsruhe to achieve a heat flux of at least 10 MW/m2. The divertor conceptual design is based on the use of a tile made of tungsten, a structural element made of tungsten alloy, and a steel cartridge. The cooling of the divertor module is realized by an impingement of helium jets (10 MPa, 600 °C) flowing through an array of small jet holes located at the top of the cartridge, able to remove the high heat flux incident on the top surface of the tiles.In this paper a modular design of a helium cooled divertor is introduced. A method of design examination regarding the cooling capability and the component stresses are pointed out. The method is based on the use of a combined system of modern computer tools. For the 3D design construction, the CAD program CATIA V5 was utilized. The simulation calculations were performed in two steps: thermo-hydraulic CFD calculations using the ANSYS CFX tool and thermo-mechanical FEM calculations with the ANSYS code. The CFD computations were done taking into account the design geometry with an appropriate meshing and the boundary conditions, i.e. the defined heat flux, the helium pressure and temperature at the inlet. Among other things, the heat-transfer-coefficients received from the CFD runs were then used for the following FEM analyses. The simulation results and a potential of design improvement will be discussed.