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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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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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.”
S. Smolentsev, N. B. Morley, M. Abdou
Fusion Science and Technology | Volume 50 | Number 1 | July 2006 | Pages 107-119
Technical Paper | doi.org/10.13182/FST06-A1226
Articles are hosted by Taylor and Francis Online.
In the dual-coolant lead lithium (DCLL) blanket, the key element is the flow channel insert (FCI) made of a silicon carbide composite (SiCf /SiC), which serves as electric and thermal insulator. The most important magnetohydrodynamic (MHD) and thermal issues of the FCI, associated with MHD flows and heat transfer in the poloidal channel of the blanket, were studied with numerical simulations using the U.S. DEMO DCLL design as a prototype. The mathematical model includes the two-dimensional momentum and induction equations for a fully developed flow and the three-dimensional (3-D) energy equation. Two FCI modifications, one with no pressure equalization openings and one with a pressure equalization slot, have been considered. The computations were performed in a parametric form, using the electric and thermal conductivity of the SiCf /SiC as parameters. Under the DEMO reactor conditions, parameters of the FCI have been identified that result in low MHD pressure drop and low heat leakage from the breeder into the helium flows. This paper also discusses the role of the pressure equalization openings, 3-D flow effects, and the effect of SiCf /SiC anisotropy.