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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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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.
Masatoshi Nakagawa, Yasusi Tsuboi
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 345-360
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34456
Articles are hosted by Taylor and Francis Online.
A new analytical method is introduced to determine the distortion and mechanical behavior of fuel-pin bundles in a wire-wrapped fuel subassembly for liquid-metal fast breeder reactor cores. Each fuel pin is considered as an elastic beam using a model that takes wire tension effects into account. To represent the nonlinear stiffness resulting from contact between the pins and the duct, a fictitious element (the joint element) is inserted at the point of contact. This element can also represent friction effects. A substructure method and a block successive overrelaxation method are used to reduce computing time and memory requirements. This analytical method was incorporated into a three-dimensional finite element code called ÉTOILE. Sample calculations are presented that show that this code is capable of a reasonable simulation of the mechanical behavior of a fuel-pin bundle during irradiation. In particular, it has been shown that wire tension has a significant effect on the fuel-pin bundle equilibrium configuration.