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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
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.