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.
Revue:
Nuclear Fusion

ISSN: 1741-4326,  0029-5515

Année de publication: 2015

Volumen: 55

Número: 9

Type: Article

DOI: 10.1088/0029-5515/55/9/093003 GOOGLE SCHOLAR lock_openAccès ouvert editor
La source de données: Scopus