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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
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 Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
N. S. Klimov, V. L. Podkovyrov, A. M. Zhitlukhin, A. D. Muzichenko, D. V. Kovalenko, A. B. Putrik, I. B. Kupriyanov, R. N. Giniyatulin, A. A. Gervash, V. M. Safronov
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 118-124
Technical Paper | doi.org/10.13182/FST13-759
Articles are hosted by Taylor and Francis Online.
The beryllium (Be) plasma-facing components (PFCs) of the ITER first wall (FW) were tested in the plasma gun QSPA-Be under pulsed plasma heat loads of 0.5-ms duration relevant to those expected in ITER during transient plasma events (edge-localized modes and disruptions). The experiments were performed for different Be grades (Russian TGP-56FW and US S65-C). The measured Be melting threshold decreases from 0.5 MJm−2 down to 0.4 MJm−2 with Be initial temperature increasing in the range of 250–500 °C. Under plasma heat loads on the exposed surface below the melting point the Be PFC erosion was mainly due to melting of the plasma-facing and lateral edges of the Be tiles. Under plasma heat loads above the melting point the Be PFC erosion was mainly due to intense melt layer movement and splashing. The Be melt layer behavior at 0.5 and 1.0 MJm−2 is similar to early investigated W melt layer behavior at higher heat loads of 1.0 and 1.5 MJm−2 correspondingly. Unlike W the Be erosion rate significantly increases with initial temperature in the range of 250–500 °C. These experimental observations are supported by calculation of temperature dynamics and melt layer thickness dynamics.