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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Fusion Science and Technology
Latest News
U.K., Japan step up progress toward fusion power demonstrations
Japan’s recent moves to boost fusion power in the nation’s energy plan and accelerate the timeline for a prototype fusion power plant come in response to increased global attention on fusion energy. Even as ITER faces delays, more than 40 private fusion developers are pursuing different technologies and competing for attention. And so are other countries, including the United Kingdom, which announced its plans for a fusion pilot plant back in 2019. Fusion companies and nations alike are responding to a growing sense that there is a race—or at least collective momentum—to commercialize fusion energy.
Takuya Nagasaka et al.
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 876-880
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST05-A797
Articles are hosted by Taylor and Francis Online.
Tungsten (W) coating on fusion candidate V-4Cr-4Ti (NIFS-HEAT-2) substrate was demonstrated with plasma spray process for the purpose of applying to protection of the plasma facing surface of a fusion blanket. Increase in plasma input power and temperature of the substrate was effective to reduce porosity of the coating, but resulted in hardening of the substrate and degradation of impact property at 77 K. The hardening seemed to be due to contamination with gaseous impurities and deformation by thermal stress during the coating process. Since all the samples showed good ductility at room temperature, further heating seems to be acceptable for the vanadium substrate. The fracture stress of the W coating was estimated from bending tests as at least 313 MPa, which well exceeds the design stress for the vanadium structure in fusion blanket.