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Development of OPR1000 RCS Hot-leg surge nozzle thermal sleeve remote removal system
| DC Field | Value | Language |
|---|---|---|
| dc.contributor.author | Kim, Younkyu | - |
| dc.contributor.author | Park, Sunkyu | - |
| dc.contributor.author | Seo, TaeWon | - |
| dc.date.accessioned | 2024-11-28T17:00:45Z | - |
| dc.date.available | 2024-11-28T17:00:45Z | - |
| dc.date.issued | 2024-10 | - |
| dc.identifier.issn | 0029-5493 | - |
| dc.identifier.issn | 1872-759X | - |
| dc.identifier.uri | https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/197758 | - |
| dc.description.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. | - |
| dc.format.extent | 7 | - |
| dc.language | 영어 | - |
| dc.language.iso | ENG | - |
| dc.publisher | Elsevier BV | - |
| dc.title | Development of OPR1000 RCS Hot-leg surge nozzle thermal sleeve remote removal system | - |
| dc.type | Article | - |
| dc.publisher.location | 스위스 | - |
| dc.identifier.doi | 10.1016/j.nucengdes.2024.113436 | - |
| dc.identifier.scopusid | 2-s2.0-85198059930 | - |
| dc.identifier.wosid | 001271623400001 | - |
| dc.identifier.bibliographicCitation | Nuclear Engineering and Design, v.427, pp 1 - 7 | - |
| dc.citation.title | Nuclear Engineering and Design | - |
| dc.citation.volume | 427 | - |
| dc.citation.startPage | 1 | - |
| dc.citation.endPage | 7 | - |
| dc.type.docType | Article | - |
| dc.description.isOpenAccess | N | - |
| dc.description.journalRegisteredClass | scie | - |
| dc.description.journalRegisteredClass | scopus | - |
| dc.relation.journalResearchArea | Nuclear Science & Technology | - |
| dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
| dc.subject.keywordPlus | Nozzles | - |
| dc.subject.keywordPlus | Nuclear fuels | - |
| dc.subject.keywordPlus | Preventive maintenance | - |
| dc.subject.keywordPlus | Ultrasonic testing | - |
| dc.subject.keywordAuthor | Nuclear power plant | - |
| dc.subject.keywordAuthor | Nuclear robot operation system | - |
| dc.subject.keywordAuthor | RCS Hot-leg | - |
| dc.subject.keywordAuthor | Thermal sleeve | - |
| dc.identifier.url | https://www.sciencedirect.com/science/article/pii/S0029549324005363?via%3Dihub | - |
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