Thermo-fluid dynamics and corrosion analysis of a self cooled lead lithium blanket for the HiPER reactor

1. Juárez, R.
2. Zanzi, C.
3. Hernández, J.
4. Sanz, J.

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DOI: 10.1088/0029-5515/55/9/093003 GOOGLE SCHOLAR lock_openOpen access editor

Data source: Scopus