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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.
Takanari Ogata, Takeshi Yokoo
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 113-123
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT99-A3018
Articles are hosted by Taylor and Francis Online.
An irradiation behavior analysis code for metallic fast reactor fuel, ALFUS, has been revised so that it can be applied to stress-strain analysis of U-Pu-Zr ternary fuel pins. The stress-strain calculation in ALFUS is closely coupled with models for slug deformation mechanisms, such as swelling due to accumulation of fission gas bubbles and nongaseous fission products. These models include the key parameters: threshold gas swelling for open pore formation, compressibility of the open pores, and accumulation rate of nongaseous fission products. The parameter values have been determined based on theoretical or experimental considerations. An empirical model has also been introduced into ALFUS to treat the effect of the large radial cracking that is a characteristic phenomenon in the ternary fuel slug. The irradiation behaviors of the ternary fuel pins of various design specifications have been analyzed using ALFUS. The analytical results are in fair agreement with the measured data for fission gas release, slug axial elongation, and cladding deformation. The calculated histories of swelling components can reasonably explain the dependency of measured cladding strain data on burnup and initial fuel smear density. One may conclude that ALFUS is valid for irradiation behavior analysis of the metallic fuel pin and is applicable to a wide range of fuel pin specifications. The methodology developed for ALFUS can be a basis for the design procedure for the metallic fuel pin.