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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
E. Wakai, T. Kikuchi, T. Yokomine, M. Yamamoto, M. Soldaini, A. Polato
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 246-251
IFMIF | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14142
Articles are hosted by Taylor and Francis Online.
International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activity (IFMIF/EVEDA) was started in 2007 in the joint program between Japan (JA) and the European Union (EU). IFMIF has mainly three facilities, i.e., test facility, lithium target facility, and accelerator facility. In this program, there are three subjects of the JA team in the test facility such as the design of the post irradiation examination (PIE) facility, the design and validation of the high flux test module, and the evaluation of the small size specimen technique. In this paper, the test matrix of the IFMIF was evaluated. All test matrixes depend on the requirement of a database preparation schedule and the irradiation volume of irradiation modules such as high flux test module (HFTM), medium flux test module (MFTM) and low flux test module (LFTM), but the engineering design of HFTM is mainly proceeding. Accordingly, the lists of the experiments of small size specimens set in the HFTM to be performed in the PIE laboratories have been carefully analyzed. In the design of HFTM, two types of HFTM are proposed for RAFM steel irradiation by the EU KIT team and for the advanced materials by the JA team, and the difference was summarized.