Ultrasonic Doppler Velocimetry Experiment of Lead-Lithium Flow with Oroshhi-2 Loop. (3rd October 2017)

• Record Type: Journal Article
• Authors: Ueki, Yoshitaka; Noguchi, Yuya; Yagi, Juro; Tanaka, Teruya; Yokomine, Takehiko; Hirabayashi, Masaru; Ara, Kuniaki; Kunugi, Tomoaki; Sagara, Akio
• Is Part Of: Fusion science and technology. Volume 72:Number 3(2017)
• Page Start: 530
• Page End: 536
• Publication Date: 2017-10-03
• Subjects: Lead-lithium -- liquid metal -- velocity profile measurement -- ultrasonic Doppler velocimetry; Fusion reactors -- Periodicals; Nuclear fusion -- Periodicals; Fusion reactors; Nuclear fusion; Periodicals; 621.48405
• DOI: 10.1080/15361055.2017.1330636
• Languages: English
• ISSNs: 1536-1055

Abstract

Abstract: The lead-lithium eutectic alloy (PbLi) is a promising coolant for nuclear fusion reactors. Although PbLi flow and heat transfer in a nuclear fusion reactor condition needs to be comprehended, no velocity profile measurement techniques have been developed yet. Since PbLi is a high-temperature liquid metal, ultrasonic Doppler velocimetry (UDV) is a promising method. In the present study, we investigated a UDV measurement in a high-purity PbLi forced convection loop environment. In summary, naturally contained oxide particles as flow tracers could differ by PbLi purity, and this difference could influence UDV measurability.