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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
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.