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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
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.
S. Masuzaki, M. Kobayashi, M. Tokitani, N. Ashikawa, T. Hino, Y. Yamauchi, Y. Nobuta, N. Yoshida, M. Miyamoto, R. Sakamoto, J. Miyazawa, T. Morisaki, N. Ohyabu, H. Yamada, A. Komori, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 321-330
Chapter 7. Plasmas-Wall Interactions | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10818
Articles are hosted by Taylor and Francis Online.
A global particle balance study has been investigated in the Large Helical Device (LHD) in which the first wall and the divertor tiles are made of stainless steel (SUS-316L) and carbon, respectively. The carbon area is less than 10% of the stainless steel area. The analyzed discharges have been conducted under an intrinsic helical divertor (HD) or a local island divertor (LID). The HD is an open divertor at this stage, and the LID is a closed divertor equipped with a baffle structure and a pump system. In the HD configuration, fuel retention up to 75% of injected hydrogen was observed, and the retained hydrogen affected the plasma density control. On the other hand, almost all fueled hydrogen was evacuated by the pumps in the LID configuration. After each experimental campaign, detailed analyses of the in-vessel material probes (SUS-316L stainless steel) and a divertor tile exposed to various plasma discharges during each experimental campaign were conducted. The areal density of the retained hydrogen both in the material probes and the divertor tile was in the range 1021 to 1022 H/m2 , and it corresponded to the averaged areal density that was observed after an experimental day with high-density discharges.