Characteristics of Frictional Pressure Drop of Heavy Liquid Metal Flow in a Single Fuel Rod Simulator
Motivated by the development of Lead alloy cooled Fast Reactors (LFR) and Accelerator Driven Systems (ADS) dedicated for the transmutation of long-lived fission products, experiments were performed on the TALL test facility at KTH to investigate thermal-hydraulics of an annular channel accommodating a single fuel rod simulator cooled by lead bismuth eutectic (LBE). The annular channel is formed in such a way that its flow area is equivalent to the subchannel around one pin in the hexagonal assembly of fuel bundle arrangement. This paper presents the friction characteristics of LBE flow through the annular channel as well as a straight tube in the intermediate heat exchangers (IHX) at various thermal-hydraulic conditions, which are of importance to the design of the cores and the IHX in the lead alloy cooled systems. The pressure drops of LBE flow in the annulus are compared with those obtained for LBE flow in the tube to see how the channel characteristics affect flow resistance.
Fast reactor heavy liquid metal flow resistance frictional pressure drop
Weimin Ma Aram Karbojian
Division of Nuclear Power Safety, Royal Institute of Technology (KTH) Roslagstullsbacken 21, 106 91 Stockholm, Sweden
国际会议
上海
英文
1564-1573
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）