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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.
P. Ihle
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 206-219
Technical Paper | doi.org/10.13182/NSE84-A18578
Articles are hosted by Taylor and Francis Online.
The results of flooding experiments with blocked arrays (FEBA) are presented, a program performed at Kernforschungszentrum Karlsruhe within the framework of the Project Nuclear Safety (PNS). Experiments performed out of pile show that coolant channel constrictions of up to 90% do not lead to significant core coolability problems during reflood. This is even true for low water injection rates corresponding to a flooding velocity of 2 cm/s for the cold bundle. The results of the thermal-hydraulic experiments cover rather widely the cladding temperature range below 1000°C. However, outlining the total range of heat transfer conditions in severely damaged rod bundle geometries, investigations performed within the framework of the PNS are mentioned as well. They provide information about the condition of rod bundles being exposed to temperatures of up to 2000°C prior to reflood.