2017•Atomic Energy Society of JapanRequires access

Thermal-hydraulic numerical evaluation for thermal striping of sodium-cooled fast reactor

Masaaki Okano

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Key concepts: Sodium-cooled fast reactor, Thermal hydraulics, Nuclear engineering, Thermal, Sodium, Data striping, Environmental science, Materials science

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Thermal-hydraulic numerical evaluation for thermal striping of sodium-cooled fast reactor — Research Paper | ScholarLens