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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
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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July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
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.
R. Sakamoto, H. Yamada, M. Kobayashi, J. Miyazawa, S. Ohdachi, T. Morisaki, S. Masuzaki, M. Goto, H. Funaba, I. Yamada, K. Ida, S. Morita, B. J. Peterson, N. Ohyabu, A. Komori, O. Motojima, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 53-60
Chapter 3. Confinement and Transport | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10793
Articles are hosted by Taylor and Francis Online.
An interesting high-density operational regime with an internal diffusion barrier (IDB) has been extended to the helical divertor configuration in the Large Helical Device. The IDB is characterized by steep density gradient in core plasma and the attainable central density exceeds 1 × 1021 m-3 at the moderate magnetic field [approximately]2.5 T while keeping relatively low density mantle plasma surrounding the core. In the IDB discharge, significant central pressure rise is observed, and the maximum central pressure attains 150 kPa by optimizing magnetic configuration. Such a high central pressure causes very large Shafranov shift, more than half radius, even at high magnetic field. Core fueling is absolutely essential for the IDB formation, and the IDB is reproducibly obtained by employing intensive multiple-pellet injections. The attainable density is restricted by lack of heat deposition at core plasma due to strong attenuation of a neutral beam in the high-density plasma.