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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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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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.
Peter Weimar, Wolfgang Ernst
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 81-89
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16188
Articles are hosted by Taylor and Francis Online.
Until now, experience with the consequences of longer operation of failed mixed oxide fuel pins in liquid-metal fast breeder reactor has not been available. Mol-7B, an 18-pin bundle, was originally specified and fabricated to test the SNR-300-Mk-Ia concept under extreme operating conditions, especially with a cladding temperature of 973 K. Because of larger uncertainties of flux distribution in the BR-2 reactor in Mol, Belgium, this bundle was irradiated with a rod power that was 20% higher as expected. As a consequence, 17 of the 18 pins failed during the irradiation campaign. The main reason was mechanical interaction of the fuel with the embrittled and corroded cladding and excessive fission gas pressure. Cladding opening was followed by chemical reaction between sodium coolant and the fuel. A partial blockage occurred from the buildup of the reaction product Na3MO4 and from the diameter increase due to uranate swelling. In spite of these severe failures and large fuel release to the coolant, the bundle could be operated with a high nominal rod power without cladding melting and more severe consequences on bundle integrity and on reactor safety.