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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.
L. Green, J. T. Kriese, M. Natelson
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 186-204
Technical Paper | Fuel | doi.org/10.13182/NT77-A31723
Articles are hosted by Taylor and Francis Online.
The reactivity perturbation method has been investigated as a possible technique for the assay of spent fuel rods from a 233UO2-ThO2-fueled core. A hard interrogating spectrum was provided at the center of the ARMF-1 core by two B4C filters of different thickness. Rods up to 267 cm (2.67 m) long were pulled through the core at speeds up to 25 cm/min (4.17 × 10−2 m/s), and the time-integrated reactivity worth was measured. The fuel response of both filters was found to be linear over a wide fuel density range, with good fuel sensitivity. Fission product sensitivities for the two filters, obtained both experimentally and calculationally, were very low and in good agreement with one another. Single-measurement uncertainty was 0.6 g at the 25 cm/min (4.17 × 10−3 m/s) pulling speed. Total estimated assay precision, including both systematic and random errors, for a hypothetical assay of 500 rods was ∼0.5%.