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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
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
Yutaka Furuta, Akira Tsuruo, Shun-ichi Miyasaka, Kozo Tamura,Yoshihiko Kanemori
Nuclear Science and Engineering | Volume 25 | Number 1 | May 1966 | Pages 85-92
Technical Paper | doi.org/10.13182/NSE66-A17504
Articles are hosted by Taylor and Francis Online.
Dose buildup factors for a plane monodirectional source of 60Co were obtained experimentally for plane parallel barriers composed, respectively, of water, graphite, ordinary glass, aluminum, ordinary concrete, heavy concrete, iron, and lead. For water, aluminum, ordinary concrete, iron, and lead, comparisons were made between the experimental and the theoretical values that were calculated by a method to obtain dose buildup factors of finite barriers. The results showed these values to be in good agreement for all materials except water. For water, further calculation by the Monte Carlo method supported the theoretical value.