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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.
Karl O. Ott
Nuclear Science and Engineering | Volume 64 | Number 2 | October 1977 | Pages 452-464
Technical Paper | doi.org/10.13182/NSE77-A27382
Articles are hosted by Taylor and Francis Online.
An approach for the description and evaluation of the uncertainties in the predicted consequences of fast breeder reactor accidents is outlined. All uncertainties are viewed as uncertainties of parameters, either of physical parameters or of quantities that appear in the parameterization of phenomenological models. By the incorporation of parameter uncertainties in the simulation of the accident progression, single accident-path scenarios assume the character of “accident spectra.” The progression of accident spectra is found by combining deterministically calculated accident-path results with the probability of the respective set of input parameters. The substantial method development needed for the implementation of the approach is discussed, and the status of the development is briefly reviewed. Typical results are presented for illustration purposes. The possible eventual significance of the approach is indicated.