UVP Measurement of Lead-Lithium Flow and Nuclear Fusion Engineering Research

Abstract

  UVP is one of promising measurement techniques for liquid-metal flows. Lead-lithium is the liquid metal which is a promising candidate of coolant in a nuclear fusion reactor. The present article is a summary of a series of UVP experiments of lead-lithium flows, and related investigations. In addition, prospects of the UVP experiments and development are described.