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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.
Yunzhao Li, Kai Huang, Hongchun Wu, Liangzhi Cao
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 49-69
Technical Paper | doi.org/10.1080/00295639.2017.1297079
Articles are hosted by Taylor and Francis Online.
The depletion systems defined by the general purpose evaluated nuclear data libraries are unnecessarily complex for most applications in nuclear reactor physics analysis. However, the corresponding compression methods are confronted with two difficulties. On one hand, the number of possible compressed depletion systems is excessively large. On the other hand, the complicated neutronic-depletion coupling effects should be properly considered. In spite of the legacy empirical-based or semi-empirical-based methods, a generalized depletion system compression method based on quantitative significance analysis is proposed in this paper. First, a quantitative significance pair was defined for each basic unit compression operation (BUCO) with respect to the neutron production density, neutron absorption density, and number densities of selected important nuclides. Second, a series of representative problems was composed according to the problem definition domain and simulated by using the original depletion system. Third, the significance pairs were evaluated based on the simulation results of the representative problems, and then employed as the quantitative guidance for accepting or rejecting each BUCO. The commpressed depletion systems have been obtained based on the newly proposed method, and typical pressurized water reactor problems were employed to verify the compresssed depletion systems. Numerical results demonstrated that by adopting the compressed depletion systems generated by the proposed method, significant computing time and storage savings can be achieved while maintaining demanded accuracy.