Rapid heating tube rupture simulation experiments in case of sodium-water reaction in steam generator of sodium-cooled fast reactor, 2

Kurihara, Akikazu ; Umeda, Ryota ; Shimoyama, Kazuhito 

Overheating tube rupture of adjacent tubes arises from water/steam leak in steam generators of sodium-cooled fast reactors. It is very important to predict the tube wall stress (tube wall temperature) with a high degree of accuracy on evaluation of overheating tube rupture, and is crucial to estimate quantitatively material strength standard which is one of the major influencing factor. In this report, rapid heating tube rupture experiments were conducted on the double-walled tube (Mod.9Cr-1Mo steel) under the same experimental conditions as those in the single-walled tube experiments, and evaluated quantitatively failure hoop stress and failure time. The authors confirmed the validity of the existing stress strength standard under the conditions that the double-walled tubes were uniformly heated.