抄録
The specification and core and structural design of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor (PBWFR) are described. Experimental studies performed for the development of the PBWFR are reported, i. e. a plan for the study on Pb-Bi-water direct contact boiling two-phase flow and heat transfer in a chimney, and the present status of the study on oxygen control and measurement in the injection of hydrogen-containing steam into a hot Pb-Bi pool.
