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

Author: JuárezR.   ZanziC.   HernándezJ.   SanzJ.  

Publisher: IOP Publishing

E-ISSN: 1741-4326|55|9|93003-93014

ISSN: 0029-5515

Source: Nuclear Fusion, Vol.55, Iss.9, 2015-09, pp. : 93003-93014

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