Development of OPR1000 RCS Hot-leg surge nozzle thermal sleeve remote removal system

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초록

The OPR1000-type reactor incorporates seven thermal sleeves (T/S) within the reactor cooling system (RCS) piping line, constructed from Inconel-600 or Inconel-690 material, depending on the power plant. In instances involving T/S made of Inconel-690 material, certain issues were identified either initially or at the commencement of operations. Consequently, the T/S installed on the safety injection nozzle was promptly removed. However, the T/S affixed to the hot-leg surge nozzle remained in operation without removal. Subsequent ultrasonic testing, conducted as part of the scheduled preventive maintenance period, revealed that the T/S associated with the hot-leg surge nozzle in the RCS pipe exhibited protrusions attributable to eccentricity and groove wear. Consequently, the removal of the T/S became imperative. This study delineates the development timeline of a remote system and highlights significant milestones achieved in the removal of the hot-leg surge nozzle T/S during the planned preventive maintenance period.

키워드

Nuclear power plantNuclear robot operation systemRCS Hot-legThermal sleeveNozzlesNuclear fuelsPreventive maintenanceUltrasonic testing
제목
Development of OPR1000 RCS Hot-leg surge nozzle thermal sleeve remote removal system
저자
Kim, YounkyuPark, SunkyuSeo, TaeWon
DOI
10.1016/j.nucengdes.2024.113436
발행일
2024-10
유형
Article
저널명
Nuclear Engineering and Design
427
페이지
1 ~ 7