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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.
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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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Fusion Science and Technology
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A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
T. Seki, T. Mutoh, R. Kumazawa, K. Saito, Y. Nakamura, M. Sakamoto, T. Watanabe, S. Kubo, T. Shimozuma, Y. Yoshimura, H. Igami, K. Ohkubo, Y. Takeiri, Y. Oka, K. Tsumori, M. Osakabe, K. Ikeda, K. Nagaoka, O. Kaneko, J. Miyazawa, S. Morita, K. Narihara, M. Shoji, S. Masuzaki, M. Goto, T. Morisaki, B. J. Peterson, K. Sato, T. Tokuzawa, N. Ashikawa, K. Nishimura, H. Funaba, H. Chikaraishi, N. Takeuchi, T. Notake, H. Ogawa, Y. Torii, F. Shimpo, G. Nomura, M. Yokota, C. Takahashi, A. Kato, Y. Takase, H. Kasahara, M. Ichimura, H. Higaki, Y. P. Zhao, J. G. Kwak, H. Yamada, K. Kawahata, N. Ohyabu, K. Ida, Y. Nagayama, N. Noda, T. Watari, A. Komori, S. Sudo, O. Motojima, LHD Experimental Group
Fusion Science and Technology | Volume 50 | Number 2 | August 2006 | Pages 186-191
Technical Paper | Stellarators | doi.org/10.13182/FST06-A1234
Articles are hosted by Taylor and Francis Online.
The long-pulse plasma discharge experiment is an important experiment in the Large Helical Device, which has a superconducting coil system and the capability of steady-state operation. The experiment of long-pulse plasma discharge was carried out using mainly ion cyclotron range of frequencies heating. The maximum plasma duration is 31 min and 45 s, and the total injected heating energy reached 1.3 GJ. Swing of the magnetic axis is adopted as an effective method to scatter the local heat load on the divertor plate during the discharge. The plasma was terminated abruptly by the influx of metallic impurities accompanied by a spark in the vacuum vessel.
