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November 16–19, 2020
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Fusion Science and Technology
U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Y. Chikhray, S. Askerbekov, Y. Kenzhin, Y. Gordienko, E. Ishitsuka
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 494-502
Technical Paper | dx.doi.org/10.1080/15361055.2020.1718854
Articles are hosted by Taylor and Francis Online.
The investigation of the mechanisms and dynamics of hydrogen isotopic interaction with solid surfaces (metals, ceramics, graphites, eutectics) in temperature and pressure ranges is important not only for the correct prediction of each isotope’s evolution but also for substantiation of the safe operation of hydrogen-facing structural materials. The interaction of the hydrogen isotopes mix with the surface of solid metal or liquid eutectics is a complicated multistage H-D-T-O-solid interacting process depending on material property, environment, and the solid’s surface parameters. To better understand the mechanisms of hydrogen isotopes interchange at a solid surface and to identify the limiting stages in the sorption-desorption processes, a reactor experiment of neutron irradiation was conducted with lithium-containing eutectics as tritium-generating media under the external flow of hydrogen. This work presents the model and results of its application to fitting the experimental results of tritium yield from the lithium-lead eutectics Pb83Li17 under thermal neutrons irradiation at the IVG.1M reactor in Kazakhstan. The elaborated model and the approach used were also applied to the simulation of high-temperature gas-cooled reactor graphite corrosion in water vapors.