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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!
Latest Magazine Issues
Apr 2025
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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.
Seiki Ohnishi, Fumiyoshi Nobuhara, Yoshihiro Hirao
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 517-526
Note | doi.org/10.1080/00295639.2023.2172309
Articles are hosted by Taylor and Francis Online.
Photon deep penetration calculations were conducted to create a buildup factor database for a new point kernel code. The calculations included the effects of photonuclear reactions, which were not considered in previous buildup factor calculations, and the target energy was extended up to 30 MeV. For media with large photonuclear cross sections, the contribution of the neutron dose becomes significant. For example, in iron at 80 mean free paths, the total dose is 1024 times larger than when the photonuclear reactions are not considered. On the other hand, it was found that if photonuclear reactions are ignored, the calculation results are not necessarily conservative in media with a significant neutron shielding capacity, such as water.
