Abstract : For stress corrosion crack(SCC) of Inconel 600, on the opportunity of the leak issue of the reacter vessel he ad nozzle at Bujey-3 in 1991, MHI has been engaged in reseach and development about the field of evaluation, maintenanc e and inspection for the part using Inconel 600 on RCS pressurized boundary. In this report, it introduces about the tec hnique of preventive maintenance for the part using Inconel 600, which have been developed or under development by MHI....
英字タイトル:
Technique of Preventive Maintenance for part using Inconel 600

Preventive maintenance techniques against PWSCC found in Alloy 600 welds have been applied progressively, however, in February 2008, a defect of PWSCC had been found in an outlet nozzle to safe-end weld of Reactor vessel of PWR in Ohi Nuclear Power Station Unit 3 during an outage. Then the defect was removed and after its safety was confirmed, the unit was placed in operation. In the next outage, INLAY method using the cylindrical container was applied an d repair welding for the removed part was performed...
英字タイトル:
INLAY Method Using the Cylindrical Container for Reactor Vessel Outlet Nozzle of PWRfor Ohi Nuclear Power Station