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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
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Satoshi Fukada, Makoto Okada, Yuki Edao, Hiroaki Okitsu, Shunsuke Yoshimura
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 636-640
Test Blanket, Fuel Cycle, and Breeding | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19163
Articles are hosted by Taylor and Francis Online.
Hydrogen permeation is investigated in a conjugated system of Li15.8Pb84.2 eutectic alloy or Ar under natural convection inside a cylindrical vertical sus316 tube. Two different temperature conditions are made between the upper and lower parts of the vertical tube. When thermal convection in Pb-Li or Ar with inside temperature distribution is fast, the rate-determining step for overall permeation rate is considered H2 permeation through the sus316 tube wall maintained at the lower temperature. On the contrary, when the inside convection is slow, the convection affects the transient behavior of overall H2 permeation rates. The analytical result was consistent with experimental ones of the Ar convection system. However, the steady-state overall H2 permeation rate for the Pb-Li system was much higher than the value estimated from the intrinsic permeability of sus316, and the values changed gradually with elapsed time. This may be because hydrogen is present as an atomic state in the Li17Pb83 convection layer with different temperatures, and bubbles on interfaces affect permeation. The overall H2 permeation rates under various temperature conditions are compared, and the effect of thermal convection is discussed.