1. Conceptual Design of a Lead-Bismuth Cooled Fast Rector with In-Vessel Direct-Contact Steam Generation, MIT-ANP-TR-079, Center for Advanced Nuclear Systems Massachusetts Institute of Technology;Buongiorno,2001
2. 7 MPa Commissioning of Two-phase Flow Loop for Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor;Pramono,2004
3. Design of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR);Takahashi,2003
4. Research Study for Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor;Takahashi,2003
5. Design and Experimental Study for Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR);Takahashi,2004