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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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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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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.”
Michel Amblard, Jean-Marc Delhaye, Karine Froment, Jean-Marie Seiler, Bruno Tourniaire
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 315-325
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3710
Articles are hosted by Taylor and Francis Online.
In the ANAIS experiments, water was injected as a jet or a spray at a given temperature and a given flow rate onto a superheated (~1600°C) molten steel layer for an imposed value of the heat rate delivered to the steel layer by induction heating. At the beginning of a test, water was injected during a few seconds with a high flow rate. Thereafter, the flow rate was decreased to evacuate the thermal power under steady-state conditions. The heat generation rate in the metal was maintained during the water injection at ~1 MW/m2, which represents a typical reactor situation. The test results showed that the steel-water heat transfer led to different final situations depending on the injection mode and water velocity. In addition, the water-cooling power was rather high at the very beginning of the transient and comparable to the heat rate delivered to the metal layer in steady-state conditions. Also, it was observed that no steam explosion occurred in any case, and that a solid layer always formed at the steel free-surface.