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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
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Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Renato Vinicius A. Marques, Marcia Saturnino, Felipe Martins, Carlos Eduardo Velasquez Cabrera, Claubia Pereira Bezerra Lima, Maria Auxiliadora Fortini Veloso, Antonella Lombardi Costa
Fusion Science and Technology | Volume 76 | Number 2 | February 2020 | Pages 145-152
Technical Paper | doi.org/10.1080/15361055.2019.1704594
Articles are hosted by Taylor and Francis Online.
Lead-bismuth eutectic is used as a coolant for the fusion-fission hybrid system (FFS) based on a tokamak that enhances the transmutation of transuranic nuclides. However, this coolant does not produce enough tritium to supply the fusion reactions of the system. Therefore, the aim of this work is to evaluate the insertion of tritium breeder layers (TBLs) on the FFS to enhance tritium production. The analyzed materials for tritium production were beryllium, boron, and lithium alloys. The results indicate the most suitable material for tritium production depends on the TBL location. The results also indicate that there is a strong dependency on the position of the TBL affecting the neutronic parameters and nuclide transmutation such as criticality and fuel depletion. The reaction rates for tritium production and fuel composition after a fuel burnup were analyzed using the Monte Carlo N-Particle 5 (MCNP5) and MONTEBURNS codes.