2000•Fusion Engineering and DesignRequires access

Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER

I. V. Vitkovsky, M. M. Golovanov, V.A. Divavin, I.R. Kirillov, A.V Lipko, A. Malkov, I.A. Kartashev, V. M. Komarov, A.P. Ogorodnikov, O. Schipakin

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Key concepts: Blanket, Nuclear engineering, Thermonuclear fusion, Thermal hydraulics, Materials science, Fusion power, Lithium (medication), Stress (linguistics)

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Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER — Research Paper | ScholarLens