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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Viatcheslav V. Anisimov, Emanuela Cavalleri, Fedor I. Karmanov, Victor I. Slobodtchouk, Lioudmila N. Latysheva, Igor A. Pshenichnov, Marcello Vecchi
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 219-227
Technical Paper | doi.org/10.13182/FST01-A163
Articles are hosted by Taylor and Francis Online.
Design calculations of thermohydraulic parameters of the secondary target of the intense neutron source (INS) based on muon-catalyzed fusion (CF) (the CF-INS) are presented for a liquid deuterium-tritium (D-T) mixture. The synthesizer is connected to an external cooler by input and output pipelines. The optimal mixture composition, synthesizer layout, and dimensions are determined. The possibility of creating a D-T mixture flow with a quasi-uniform velocity distribution is demonstrated. Possible vortexes were found to be eliminated by installation of corresponding hydraulic resistance in the shape of a spherical shell segment. At the CF-INS operation with its design parameters [neutron flux as high as 1014 n/(cm2s)], the total heat deposit in the D-T mixture due to fusion and charged-particle ionization losses is estimated at ~117 kW. However, even at such conditions, with the appropriate synthesizer geometry and mass flow rate, the mixture temperature does not exceed the boiling point in any part of the synthesizer.