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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Fusion Science and Technology
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Hiroyuki Shidara, Kazunobu Nagasaki, Kinzo Sakamoto, Hidetoshi Yukimoto, Masahiko Nakasuga, Fumimichi Sano, Katsumi Kondo, Tohru Mizuuchi, Hiroyuki Okada, Sakae Besshou, Shinji Kobayashi, Yoshito Manabe, Hayato Kawazome, Tasho Takamiya, Yoshinori Ohno, Hiroyasu Kubo, Yusuke Nishioka, Masao Iriguchi, Masashi Kaneko, Koichi Takahashi, Yohei Fukagawa, Yuya Morita, Masaki Yamada, Shingo Nakazawa, Shintaro Tsuboi, Shigeru Nishio, Victor Orlov, Alexander Pavelyev, Alexander Tolkachev, Victor Tribaldos, Tokuhiro Obiki
Fusion Science and Technology | Volume 45 | Number 1 | January 2004 | Pages 41-48
Technical Paper | doi.org/10.13182/FST04-A424
Articles are hosted by Taylor and Francis Online.
A 70-GHz electron cyclotron resonance heating (ECRH) system has been constructed in a helical-axis heliotron device, Heliotron J, in order to realize localized heating and current drive experiments. Since the Heliotron J plasma has a three-dimensional complex shape, the ECRH system is designed to satisfy the requirement of wide steering capability in both the toroidal and poloidal directions. The low-power transmission test shows that the beam radius of the focused Gaussian beam is 22 mm at the magnetic axis, which is small enough compared to the averaged minor plasma radius (170 mm), and the launching system covers a wide toroidal steering range from perpendicular to tangential injection by replacing the steering plane mirror. Since these characteristics satisfy the condition for controlling the power localization in the three-dimensional helical-axis configuration, it is possible to explore the on- and off-axis heating over most of the plasma radius (0 < r/a < 0.7) and the electron cyclotron current drive. In the high-power transmission test, the transmission efficiency of the 20-m corrugated waveguide is 92%, and the available output power to the vacuum vessel is up to 0.4 MW. Plasma production and heating are successfully performed using this ECRH system.
