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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
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
M. Kobayashi, N. Ohyabu, T. Mutoh, R. Kumazawa, Y. Feng, M. Shoji, T. Morisaki, S. Masuzaki, A. Sagara, R. Sakamoto, T. Seki, J. Miyazawa, T. Watanabe, M. Goto, K. Ideda, H. Kasahara, S. Morita, B. J. Peterson, N. Ashikawa, K. Saito, S. Sakakibara, T. Tokuzawa, Y. Nakamura, K. Narihara, I. Yamada, H. Yamada, A. Komori, O. Motojima, LHD Experimental Group
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 566-573
Technical Paper | The Technology of Fusion Energy - High Heat Flux Components | doi.org/10.13182/FST07-A1549
Articles are hosted by Taylor and Francis Online.
The divertor performance of LHD is studied for the two configurations, LID and HD. It is shown that the both divertor configurations play important roles for obtaining high performance plasmas in LHD: the large pumping capability of the LID to keep the low edge density in the IDB-SDC plasma, the large wetted area and the flexibility of strike point sweep of HD to reduce the power load on the divertor plates in long pulse operations. The possible effect of the ergodic layer on impurity retention in divertor is discussed by using the 3D edge transport modelling. It is found that the drag force exerted by the plasma flow can dominate over the thermal force, providing the impurity retention effect. The further changes needed to improve the current divertor configurations are discussed. New divertor designs for the future upgrade of LHD and for a LHD-type reactor are presented.
