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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
D. H. Cho, Donn R. Armstrong II, S. H. CHAN
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 23-31
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33369
Articles are hosted by Taylor and Francis Online.
An experimental study of water penetration into a hot particle bed has been conducted. The pattern of water penetration was found to be complicated due to the formation of dry pockets and channels. Overall, the water penetrates down the bed as a single column in the central region, while the annular region near the wall remains hot and dry. After the water has reached the bottom, it starts flowing back up, filling the dry channels in the annular region. One-dimensional quench models, while reasonably successful in estimating the average quench rate, would not be adequate for describing the water penetration. These findings would be of interest in assessing the potential for concrete erosion by hot core debris in the reactor cavity.