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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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Nuclear Technology
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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Alice Ying, Hongjie Zhang, Joseph Mauricio Garde, Mike Ulrickson
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 309-314
Divertor and High-Heat-Flux Components | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A18095
Articles are hosted by Taylor and Francis Online.
The impact of Be tile size on the stress exerted on the CuCrZr heat sink for the ITER EHF finger was examined. The study especially focused on the areas beneath the tiles that are exposed to the high convective heat flux. For reference, in a Be tile size of 50x50x8 mm3, the calculated equivalent strain range using elastic analysis for the path of interest through the side wall of the CuCrZr heat sink resulted in a peak value at the inner wall of ~0.492%. The corresponding fatigue lifetime of the heat sink locally is unacceptably low, 1400 cyclic operations. By using smaller tiles, lower stress amplitudes are observed due to a smaller deformation. In this paper, the total strain range under ITER projected pulsed operating conditions is analyzed for a range of Be tile sizes. The analysis model uses a complete pair of twin fingers as opposed to a sub-model of two tiles. The paper documents the calculated cyclic lifetime of the ITER EHF CuCrZr heat sink with respect to Be tile size and peak heat loads by evaluating the total strain range both from elastic and time independent elasto-plastic analyses for repeated cycle.