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

Authors
Kim, YounkyuPark, SunkyuSeo, TaeWon
Issue Date
Oct-2024
Publisher
Elsevier BV
Keywords
Nuclear power plant; Nuclear robot operation system; RCS Hot-leg; Thermal sleeve
Citation
Nuclear Engineering and Design, v.427, pp 1 - 7
Pages
7
Indexed
SCIE
SCOPUS
Journal Title
Nuclear Engineering and Design
Volume
427
Start Page
1
End Page
7
URI
https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/197758
DOI
10.1016/j.nucengdes.2024.113436
ISSN
0029-5493
1872-759X
Abstract
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.
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