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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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Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
M. Yoshinuma, K. Ida, M. Yokoyama, M. Osakabe, K. Nagaoka, S. Morita, M. Goto, N. Tamura, C. Suzuki, S. Yoshimura, H. Funaba, Y. Takeiri, K. Ikeda, K. Tsumori, O. Kaneko, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 103-112
Chapter 3. Confinement and Transport | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10797
Articles are hosted by Taylor and Francis Online.
Spontaneous toroidal flow driven by ion temperature gradient and extreme hollow profile of carbon impurity (denoted as an "impurity hole") is observed associated with the increase of ion temperature gradient in the large helical device (LHD). Spontaneous toroidal flows driven by radial electric field and ion temperature gradient are studied. The positive radial electric field drives spontaneous flow in the counterdirection at the plasma edge and in the codirection near the magnetic axis. The component of the spontaneous toroidal flow driven by ion temperature gradient is clearly observed and expected to be one of the dominant components of toroidal flows in the high-ion temperature discharges in LHD. The transport analysis of the carbon impurity in the discharge with impurity hole reveals a low diffusion coefficient and the outward convection velocity, whereas the inward convection is predicted by the neoclassical theory at half the minor radius.