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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.
Walter J. Eich, Mark L. Williams,Chun-Mou Peng
Nuclear Science and Engineering | Volume 90 | Number 2 | June 1985 | Pages 127-139
Technical Paper | doi.org/10.13182/NSE85-A17671
Articles are hosted by Taylor and Francis Online.
Analysis of critical experiments for cross-section evaluation has been conducted on the basis of one-dimensional four-group diffusion theory calculations that explicitly model the homogenized core and reflector in the radial plane. Such analyses require a reflector representation that models the leakage process as accurately as feasible. The development and testing of few-group ENDF/B-V based light water reflector constants for use in diffusion theory derived to reproduce leakage and other reaction rates from reference multifast group transport calculations are described. This work has been extended to parameterize similar higher order transport calculations with two- or four-group constants valid for application to typical pressurized water reactor baffle/reflector configurations as represented in coarse mesh diffusion (PDQ) representations.