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Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Y. Ueda, H. Kashiwagi, M. Fukumoto, Y. Ohtsuka, N. Yoshida
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 85-90
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8881
Articles are hosted by Taylor and Francis Online.
Simultaneous irradiation effects of He on tungsten blistering with hydrogen and carbon mixed ion beam were investigated. It was found that only 0.1% addition of He ions to 1 keV H and C mixed ion beam (C:0.8-1.0%) reduced (at 473 K) or completely suppressed (at 653 K and 723 K) blister formation. In order to obtain more detailed result, two ion sources were used to irradiate tungsten with H and He ions with different energies. In the He energy of 0.6 keV (1.5 keV H&C),significant blistering was observed, while in the He energies of 1.0 keV and 1.5 keV, blister formation was suppressed. These results suggested that a He bubble layer reduced hydrogen diffusion through the layer. A He bubble size and a volume rate were about 1-2 nm and ~2% at 653 K, respectively. To evaluate T retention in the ITER tungsten wall, this effect should be included.