An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction.

Lead-cooled Fast Reactors (LFRs) has become a main candidate choice among the fourth-generation reactors, and Steam Generator Tube Rupture accident (SGTR) is one kind of its important Design Extension Condition (DEC). Due to the limitations of existing theoretical research and simulation tools, many SGTR thermal-hydraulic experiments have been carried out recently. This paper reviews thermal-hydraulics stages into four stages: 1) water-LBE interaction together with steam explosion, 2) high-pressure water jet and structures impact, 3) steam bubbles transport in primary system, 4) bubble entrained and stayed in the reactor core. The existing SGTR experiments are classified as separate SGTR effect test experimental facilities and separate LBE-water interaction experimental facilities. The methods of high-pressure injection, LBE status change and parameters measurement of separate SGTR effect experimental facilities are introduced. Four experimental prospects for further research are suggested as pressure transmission and structure impact, steam lifting and visualization, bubble transport in full-scale or reduced-scale model of reactor, behaviors of LBE-water mixture. • An LFR experimental review of SGTR thermal-hydraulic experiments. • SGTR thermal hydraulic phenomena are divided. • SGTR thermal hydraulic experiments are classified into two categories. • Experimental methods introduction and further research suggestion. [ABSTRACT FROM AUTHOR]