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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
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Dongxun Zhang, Wei Liu, Wenguan Liu
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 543-552
Technical Paper | doi.org/10.1080/15361055.2020.1725368
Articles are hosted by Taylor and Francis Online.
With the method of gas-driven permeation, a series of permeation experiments was carried out using Hastelloy N alloy membrane in an elevated temperature range of 400°C to 800°C with different hydrogen isotopes. A complete set of permeability, diffusivity, and Sieverts’ constant for hydrogen and deuterium in Hastelloy N alloy was successfully obtained. The isotope effect in the diffusion process was analyzed and compared with references. The ratios of diffusive transport parameters for hydrogen and deuterium were a permeability ratio of ФH/ФD = 1.32exp(0.34kJ/RT), a diffusivity ratio of DH/DD = 1.15exp(−0.41kJ/RT), and a Sieverts’ constant ratio of KS,H/KS,D = 1.16exp(0.21kJ/RT). The result that the permeation flux of deuterium was decreased after introducing hydrogen could be used to suppress the permeation of tritium in future tritium control of the Fluoride-salt-cooled High-temperature Reactor (FHR). Compared with NiO, the Cr2O3 formed in the surface oxidation layer of Hastelloy N alloy showed better hydrogen permeation barrier performance after baking above 700°C in air.