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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.
R. D. McKnight
Nuclear Science and Engineering | Volume 75 | Number 1 | July 1980 | Pages 111-125
Technical Note | doi.org/10.13182/NSE80-A20322
Articles are hosted by Taylor and Francis Online.
A detailed validation study of the SDX fast reactor cell homogenization code, Benoist anisotropic diffusion coefficients, and an associated three-dimensional to one-dimensional unit cell modeling procedure has been in progress. These earlier results have investigated the standard zero power reactor (ZPR) plate-type unit cell The present study represents a complimentary validation effort for the ZPR pin calandria-type unit cell. The unit cell loading selected for this work consisted of a 5.08- × 5.08- × 30.48-cm voided calandria loaded with a 4 × 4 array of 0.957-cm (diam) × 15.24-cm mixed-oxide rods (15% PuO2/UO2). This unit cell was used in the pin zone measurements of the ZPR gas-cooled fast reactor program and also in the sodium-voided pin zone measurements of ZPR-6 Assembly 7. The validation effort consists of direct comparison with results of VIM (continuous energy Monte Carlo) calculations. The SDX/Gelbard methods have been shown to adequately predict both nonleakage and leakage effects for the voided pin calandria unit cell.
