Significant numbers of intergranular stress corrosion cracking incidents have occurred in welded austenitic stainless steel of primary loop recirculati on system piping in boiling water reactors. This crack was also occurred in Shika Nuclear Power unit 1. This time, stress improvement processing by hig frequency guidance overheating has been performed as preventive maintenance to the weld line with which we are anxious about generating of stress corr ion cracking among the weld lines of primary loop recirc...
英字タイトル:
Induction Heating Stress Improvement for pipe of primary loop recirculation system at Shika Nuclear Power Station Unit 1

In the Nuclear Power Station, maintenance of many equipment are performed by time-based maintenance which overhaul the equipment at the reactor outages intervals. However, there is a tendency that has become an excessive maintenance such as inspection interval is short in time-based maintenance, on the contrary there is a risk that shorten the life of the equipment is concerned. Therefore, it is promoting the introduction of condition-based maintenance to implement maintenance at the appropriate timin...
英字タイトル:
Efforts of condition based maintenance in Shika Nuclear Power Station