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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Panos J. Karditsas
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 729-733
Technical Paper | Fusion Energy - Divertor and Plasma-Facing Components | doi.org/10.13182/FST05-A772
Articles are hosted by Taylor and Francis Online.
The High Efficiency Thermal Shield (HETS) concept was proposed by ENEA for divertor application in the context of the ITER project and as part of the European Power Plant Conceptual Study. The design is modular, and the unit dimensions are of the order of centimeters for limiting mechanical and thermal stresses. This paper presents results of thermal-fluid and structural analyses, with different heat flux loads, fluid pressures and inlet velocities. The fluid analysis shows that the sharp corner flow passage at the point of flow reversal behaves like an abrupt enlargement, leading to considerable pressure losses as compared to the results obtained by rounding the corner. The combination of rounding the sharp corner and flow cross-sectional area expansion, leads to reduced pressure losses, without any degradation of the thermal performance of the component.