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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.
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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
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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.
K.E. Wright, M.E. Oldaker, G.R. Pinter
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1672-1677
Plasma Engineering | doi.org/10.13182/FST92-A29962
Articles are hosted by Taylor and Francis Online.
A new gas delivery system is being designed to inject either tritium or deuterium gas with uniform throughput for up to 6 seconds into the TFTR Neutral Beam Long Pulse Ion Sources. Several experiments have been conducted to verify design concepts and qualify components. Piezoelectric valves were characterized for hydrogen and deuterium gas and the data used to predict operation with tritium. The uniformity of the gas throughput was studied as a function of test fluid, flowrate and initial plenum pressure. Various passive techniques to mitigate unacceptable thermal effects were tested. The uniformity of the throughput with an active pressure feedback controller was tested under various operational scenarios. The functionality of a prototypical NB D-T Gas Delivery System has been analyzed. This paper presents the results of these pre-operational tests.