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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.
G. Palmiotti, M. Salvatores
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 333-348
Technical Paper | doi.org/10.13182/NSE87-333
Articles are hosted by Taylor and Francis Online.
Integral experiments play an essential role in the reduction of design uncertainties related to liquid-metal fast breeder reactor neutronics calculations. Spectrum-dependent integral parameters, such as the critical balance, have been the subject of extensive experimental studies in the various critical facility programs of the leading fast reactor programs in view of the extrapolation of the observed results to power reactors. Space-dependent parameters, such as power distribution perturbation and control rod effects, have also been the subject of large experimental programs, but it has been more difficult to find an unambiguous, systematic approach to extrapolate to the reference power reactors with the particular purpose of defining bias factors and uncertainties to be used in design calculations. Different approaches are recalled in the case of spectrum-dependent integral parameters, and some suggestions are made to define a systematic approach for the space-dependent parameters using the existing critical facilities, i.e., reduced-size cores and limited fuel inventories.