Intermediate leak wastage test of heat transfer tube of LMFBR'S steam generator (II)

not registered; not registered; not registered; Daigo, Yoshimichi

Sodium-water reaction tests were conducted at Oarai Engineering Center, PNC by using SWAT-1 (Large Sodium Water Reaction Test Rig) in the range of medium steam leak rate. These tests include, (1)determination of wastage rate on weld joint of heat transfer tube, (2)evaluation of toroidal westage on cooling heat transfertube, (3)evaluation of westage due to steam leak into cover gas phase, and (4)determination of heat transfer rate from jet flame to heat transfer tube, all of which have not been studied in the early tests. From the present tests results, the following conclusions were yield. (1)No difference was observed in wastage rate between weld metal and base metal of 2.25Cr-1Mo tube material. (2)The maximum secondary leak size of torroidal shape damage should be considered 1/2 DEG failure. (3)In case of water leak event in cover gas space, the ring shape wastage was examined in all tubes at sodium free surface level, but the wastage rate is much smaller than the direct impingement wastage in sodium. (4)The value of outer surface heat transfer coefficient was obtained.