tailieunhanh - Nuclear engineering and technology, Overall system description and safety characteristics of prototype gen iv sodium cooled fast reactor in Korea

This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper. | Nuclear engineering and technology, Overall system description and safety characteristics of prototype gen iv sodium cooled fast reactor in Korea

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