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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.”
T. R. Jarboe, C. J. Hansen, A. C. Hossack, G. J. Marklin, K. D. Morgan, B. A. Nelson, D. A. Sutherland, B. S. Victor
Fusion Science and Technology | Volume 66 | Number 3 | November 2014 | Pages 369-384
Technical Paper | doi.org/10.13182/FST14-782
Articles are hosted by Taylor and Francis Online.
The conceptual design of an experiment for demonstrating and developing the efficient sustainment of a spheromak with sufficient confinement is presented. “Sufficient” means that the current drive power can heat the plasma to its stability β limit. Previous transient experiments showing sufficient confinement in the kilo-electron-volt temperature range with no external toroidal field coil, recent results on Helicity Injected Torus with Steady Inductive (HIT-SI) showing sustainment with sufficient confinement, the potential of imposed dynamo current drive (IDCD) of solving other fusion issues, and a very attractive reactor concept justify a proof-of-principle experiment for a high-β spheromak sustained by IDCD. A machine with 1-m minor radius with the required density control, wall loading, and neutral shielding for a 10-s pulse is described. Peak temperatures of 3 keV and toroidal currents of 3.2 MA and 16% wall-normalized plasma β are envisioned.
