STATUS AND PROPOSAL STUDUIES ON THERMAL-HYDRAULIC PHENOMENA TO STEAM GENERATOR TUBE RUPTURE ACCIDENT IN LFR AND ADS
This article reviews the studies on steam generator tube rupture (SGTR) accident in lead alloy-cooled fast reactors (LFR) and the accelerator-driven transmutation system (ADS) including proposal for visualization test in injection of water into molten lead-bismuth eutectic (LBE) and lead (Pb) using neutron radiography. The SGTR and the consequent interaction between LBE/Pb and water, i. e., coolant-coolant interactions (CCI), represents an important concern for the safety of LFR and ADS since the CCI might bring a local core voiding, and even initiate a sloshing motion of liquid metal coolant to damage the vessel, which is similar with fuel-coolant interaction (FCI) in light water reactors (LWR) and sodiumcooled fast reactors. Based on the review of related studies, visualization test in special conditions using neutron radiography is proposed to investigate this transient thermalhydraulic phenomenon.
Rongyuan Sa Minoru Takahashi
Department of Nuclear Engineering, Tokyo institute of Technology Tokyo, Japan Research Laboratory for Nuclear Reactor, Tokyo institute of Technology Tokyo, Japan
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-4
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）