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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Y. Ikeda, C. Konno, T. Nakamura, A. Kumar, M. A. Abdou
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1961-1966
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29629
Articles are hosted by Taylor and Francis Online.
An experiment of Induced radioactivity and decayheat has been conducted in the framework of JAERI/USDOE collaborative program on the fusion blanket neutronics. Sixteen different materials have been irradiated in two typical DT neutron fields simulating spectra at the first wall and blanket regions of a fusion reactor. Induced radioactivity production profiles for both short and long irradiation times were analyzed by detecting associated γ-ray energy spectra. Energy release rate in material was characterized on the basis of the γ-ray emission data measured as well as β-ray contribution estimated. In this experimental study, focuses were placed not only on providing benchmark data for verification of the calculation code and nuclear data, but also on a comparative study for providing a guide line for the material selection concerning the dose rate as well as the decayheat after shutdown in the near term DT fusion devices.