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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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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Latest News
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
H.Yoshida, M.Taniguchi, K.Yokoyama, Y.Hirohata, M.Akiba, T.Hino
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 943-947
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22724
Articles are hosted by Taylor and Francis Online.
Tritium retention of carbon dust co-deposited with fuel hydrogen is large, and then it is required to evaluate the tritium inventory as a safety issue of ITER. Several species of co-deposited carbon dust were prepared by D2 arc discharge with carbon electrodes. The dependence of D2 gas pressure on the retained deuterium amount of the co-deposited dust was investigated. The structure and the surface morphology were also examined. The retained deuterium amount increased with the discharge gas pressure. The deuterium concentrations of the co-deposited carbon dust samples prepared at 1.3 Pa and 6.8 Pa were 0.12 and 0.3 in the atomic ratio, D/C, respectively. No clear dependence of the substrate temperature on retained deuterium amount was observed, perhaps due to the coarse temperature control. In the environment of gas pressure in ITER, approximately 1 Pa, the tritium concentration is estimated approximately T/C ≈ 0.06, which is several times smaller than the value estimated so far, T/C ≈ 0.2.