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Dive into the research topics of 'Thermal-hydraulic design of direct superheated steam blanket for the compact reversed shear tokamak reactor (CREST)'. Together they form a unique fingerprint.- Sort by
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Y. Nomoto, T. Ishida, H. Ise, S. Mori, Y. Asaoka, T. Yoshida, R. Hiwatari, K. Okano
Research output: Contribution to journal › Article › peer-review