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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.
Stephane Cathalau, Amal Benslimane, Abdelmajid Maghnouj, Philippe Fougeras, Vladimir Ukraintsev
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 326-333
Technical Paper | doi.org/10.13182/NSE95-A28568
Articles are hosted by Taylor and Francis Online.
The calculation of reactor design parameters with ever higher accuracy requires constant improvement in basic nuclear data and computational techniques. Several methods based on formal statistical techniques have been studied to adjust cross sections used in fast reactor design calculations; nevertheless, these techniques have never been used for epithermal and thermal energy ranges. In this study, the statistical adjustment technique is reviewed, the integral experiments that serve as the adjustment database are presented, and suggested adjustments are discussed. If the cross sections of the main heavy nuclides seem to be well known, this study shows a very strong modification of the 235U capture cross section in the resonance range (∼10%). This trend can be explained by an underestimation of the mean capture width used in the 235U evaluation. The statistical technique used in this study allows us to qualify the JEF2 cross sections with a high quality of confidence.