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May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Latest News
Canada begins regulatory approval process for spent fuel repository
Canada has formally initiated the regulatory process of licensing its proposed deep geological repository for spent nuclear fuel, with the country’s Nuclear Waste Management Organization (NWMO) announcing that it has submitted an initial project description to the Canadian government.
According to the NWMO, the initial project description is a foundational document, detailing the repository’s purpose, need, and expected benefits and explaining how the project will be implemented. It also provides a preliminary assessment of potential impacts and describes measures to avoid or mitigate them. The NWMO is the not-for-profit organization responsible for managing Canada’s nuclear waste.
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 | 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.