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Fusion Science and Technology
NRC moves ahead on HALEU enrichment, rulemaking, and guidance
The Nuclear Regulatory Commission is requesting comments on the regulatory basis for a proposed rule for light water reactor fuel designs featuring high-assay low-enriched uranium (HALEU), including accident tolerant fuel (ATF) designs, and on draft guidance for the environmental evaluation of ATFs containing uranium enriched up to 8 percent U-235. Some of the HALEU feedstock for those LWR fuels and for advanced reactor fuels could be produced within the first Category II fuel facility licensed by the NRC—Centrus Energy’s American Centrifuge Plant in Piketon, Ohio. On September 21, the NRC approved the start of enrichment operations in the plant’s modest 16-machine HALEU demonstration cascade.
Sergey Pestchanyi, Francesco Maviglia
Fusion Science and Technology | Volume 75 | Number 7 | October 2019 | Pages 647-653
Technical Paper | doi.org/10.1080/15361055.2019.1643684
Articles are hosted by Taylor and Francis Online.
Simulation of divertor target damage during thermal quench of the disruption in the future DEMO tokamak has been performed using the TOKES code. This parametric study includes damage estimation for disruptions of the plasma energy E0 in the DEMO core in the range of 0.4 to 1.3 GJ and of time duration 1 to 2 ms. According to the simulations, the maximum melt depth on the divertor targets is ~80 μm, independent of the energy content in the core. The melted pool maximum area grows from ~20 m2 for 0.4-GJ disruption to ~120 m2 for 1.3-GJ disruption. Maximum erosion depth is 4 μm for 1.3-GJ disruption and decreases to less than 1 μm with decreasing E0. The total quantity of vaporized tungsten ranges from 2 ∙ 1021 to 3 ∙ 1024 atoms for disruptions of 0.4 to 1.3 GJ. An additional parametric study has revealed weak dependence of the results from the characteristic widths λq of the disruptive flux in the scrape-off layer.