• 제목/요약/키워드: Plugging Limit

검색결과 8건 처리시간 0.026초

원전 증기발생기 전열관 관막음 한계 고찰 (A Review of Plugging Limit for Steam Generator Tubes in Nuclear Power Plants)

  • 강용석;이국희
    • 한국압력기기공학회 논문집
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    • 제16권2호
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    • pp.10-17
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    • 2020
  • Securing the integrity of steam generator tubes is an essential requirement for safe operation of nuclear power plants. Therefore, tubes that do not satisfy integrity requirements are no longer usable and must be repaired according to the related requirements. In general, the repair criterion is that the damage depth is more than 40% of the tube wall thickness. However, the plugging limit can be changed and be applied, provided a technical proof is given that integrity can be secured against specific degradation at a specific plants and that approval can be obtained from a regulatory agency. A typical example is alternative repair criteria for defects within the tube sheet or tube support plates. In this paper, a background of establishing the plugging limit for steam generator tubes and changes in maintenance criteria are reviewed as examples.

복층 및 다층장갑판재의 관통에 대한 상부경계이론 해석 (An upper bound analysis for the plugging type of ballistic perforation on the double and multi-layered armour plates)

  • 이종우
    • 한국군사과학기술학회지
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    • 제3권2호
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    • pp.35-41
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    • 2000
  • A modified theoretical analysis of the ballistic perforation on the double and multi-layered armour plates using an upper bound method has been presented in this paper. A modified model based on the suggestion of the Awerbuch-bodner model has been adapted and extended into double and multi-layered armour plates when the plugging type of penetration has been occurred. The residual projectile speed, ballistic limit velocity and contact time during the penetration process have been derived from the equation of motion at each stage.

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월성 3,4호기 증기발생기 전열관 검사 (Wolsong 3&4 Steam Generator Tube Inspection)

  • 장경식;권동기;최진혁;손태봉
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 추계학술대회논문집B
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    • pp.859-866
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    • 2001
  • During the Pre-service Inspection for Wolsong Unit 3&4 in 1997/1998 respectively, 17 Distorted Roll Transition indications(over expanded beyond tubesheet secondary face) were identified at the Unit 4 (S/G B, D). Six(6) tubes out of these tubes were plugged in 1998. However the first Periodic Inspection identified additional 110 indications in 1999 and 2000. The additionally identified 110 indication call, not reported at the Pre-service Inspection, are; 2 Not-Finally-Expanded-Tubes and 108 Distorted Roll Transition tubes. Design limit of each Steam Generator tube Plugging is 6.4%. Plugging was performed by the Steam Generator manufacturer under the warranty. When Distorted Roll Transition indications were first identified on the Unit 4 in 1998 the degree of Over-expansion was measured using an inner dial-gage to make the disposition of Nonconformance report. 2 Not-Finally-Expanded-Tubes were plugged and 10 tubes out of 108 Distorted Roll Transition Tubes were also plugged as a preventive measure.

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축방향 다중관통균열이 존재하는 증기발생기 세관 평가법 (Assessment of Steam Generator Tubes with Multiple Axial Through-Wall Cracks)

  • 문성인;장윤석;김영진;이진호;송명호;최영환
    • 대한기계학회논문집A
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    • 제28권11호
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    • pp.1741-1751
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    • 2004
  • It is commonly requested that the steam generator tubes wall-thinned in excess of 40% should be plugged. However, the plugging criterion is known to be too conservative for some locations and types of defects and its application is limited to a single crack in spite of the fact that the occurrence of multiple through-wall cracks is more common in general. The objective of this research is to propose the optimum failure prediction models for two adjacent through-wall cracks in steam generator tubes. The conservatism of the present plugging criteria was reviewed using the existing failure prediction models for a single crack, and six new failure prediction models for multiple through-wall cracks have been introduced. Then, in order to determine the optimum ones among these new local or global failure prediction models, a series of plastic collapse tests and corresponding finite element analyses for two adjacent through-wall cracks in thin plate were carried out. Thereby, the reaction force model, plastic zone contact model and COD (Crack-Opening Displacement) base model were selected as the optimum ones for assessment of steam generator tubes with multiple through-wall cracks. The selected optimum failure prediction models, finally, were used to estimate the coalescence pressure of two adjacent through-wall cracks in steam generator tubes.

두개의 평행한 축방향 관통균열이 존재하는 증기발생기 세관의 최적 파손예측모델 (Optimum Failure Prediction Model of Steam Generator Tube with Two Parallel Axial Through-Wall Cracks)

  • 이진호;송명호;최영환;김낙철;문성인;김영진
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 추계학술대회
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    • pp.1186-1191
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    • 2003
  • The 40% of wall criterion, which is generally used for the plugging of steam generator tubes, may be applied only to a single crack. In the previous study, a total of 9 failure models were introduced to estimate the local failure of the ligament between cracks and the optimum coalescence model of multiple collinear cracks was determined among these models. It is, however, known that parallel axial cracks are more frequently detected during an in-service inspection than collinear axial cracks. The objective of this study is to determine the plastic collapse model which can be applied to the steam generator tube containing two parallel axial through-wall cracks. Nine previously proposed local failure models were selected as the candidates. Subsequently interaction effects between two adjacent cracks were evaluated to screen them. Plastic collapse tests for the plate with two parallel through-wall cracks and finite element analyses were performed for the determination of the optimum plastic collapse model. By comparing the test results with the prediction results obtained from the candidate models, a plastic zone contact model was selected as an optimum model.

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다중균열 구조물의 소성붕괴거동 평가 (Evaluation of Plastic Collapse Behavior for Multiple Cracked Structures)

  • 문성인;장윤석;김영진;이진호;송명호;최영환;황성식
    • 대한기계학회논문집A
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    • 제28권11호
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    • pp.1813-1821
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    • 2004
  • Until now, the 40% of wall thickness criterion, which is generally used for the plugging of steam generator tubes, has been applied only to a single cracked geometry. In the previous study by the authors, a total number of 9 local failure prediction models were introduced to estimate the coalescence load of two collinear through-wall cracks and, then, the reaction force model and plastic zone contact model were selected as the optimum ones. The objective of this study is to estimate the coalescence load of two collinear through-wall cracks in steam generator tube by using the optimum local failure prediction models. In order to investigate the applicability of the optimum local failure prediction models, a series of plastic collapse tests and corresponding finite element analyses for two collinear through-wall cracks in steam generator tube were carried out. Thereby, the applicability of the optimum local failure prediction models was verified and, finally, a coalescence evaluation diagram which can be used to determine whether the adjacent cracks detected by NDE coalesce or not has been developed.

연료물성에 따른 경유 차량의 저온성능 영향 연구 (A Study on the cold weather performance for diesel vehicle as fuel properties)

  • 장은정;김성우;민경일;박천규;하종한;이봉희
    • 에너지공학
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    • 제24권2호
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    • pp.144-153
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    • 2015
  • 저온에서 경유의 파라핀 왁스 생성 및 침전현상은 차량의 저온성능에 악영향을 준다. 본 연구에서는 경유에 바이오디젤, 등유, 저온특성첨가제를 혼합한 연료에 대해 연료조성에 따른 담점, 필터막힘점, 유동점 변화를 분석하였고, 경유의 저온특성에 따른 차량의 저온성능에 대해 평가하였다. 경유는 유동성향상 첨가제(WAFI)와 등유유분의 혼합량이 증가할수록 저온특성이 개선되었으며, 바이오디젤 혼합량이 증가할수록 저온특성이 악화되었다. WAFI는 필터막힘점 개선에, 등유유분은 담점 개선에 효과적이었다. 차량의 저온성능에 대하여 필터막힘점과 유동점의 영향성은 확인하였으나, 담점은 큰 영향이 없었다. 필터막힘점은 차량에 대해 저온에서의 운행가능 한계를 반영하였다.

와전류탐상검사에 의한 튜브엔드 슬리브 건전성 검증 (The Integrity Verification of Tube-end Sleeve by ECT)

  • 김수진;권경주;석동화;박기태
    • 한국압력기기공학회 논문집
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    • 제11권1호
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    • pp.20-24
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    • 2015
  • Steam generator(S/G) tubes in pressurized water reactor (PWR's) are subject to several types of degradation. This degradation includes denting, pitting, intergranular attack(IGA), intergranular stress corrosion cracking(IGSCC), fatigue, fretting and wear. Degradation can be derived from either the primary side(inside) or the secondary side(outside) of the tube. Recent issue for tube degradation in domestic steam generator is the tube end cracking on seal weld region. The seal weld region at the tube end and tube itself is regarded as a pressure boundary between the primary side and the secondary side. One of the Westinghouse Model-F S/G has experienced tube end cracking and its number of plugging approximately becomes to the operating limit up to 5% due to tube end cracking which was reported as SAI/MAI(single/multiple axial indication) or SCI/MCI(Single/multiple circumferential indication) from the results of eddy current testing. Eddy current mock-up test was carried out to determine the origin of cracking whether it is from weld zone area or parent tube. This result was helpful to analyze crack location on ECT data. Correct action on this problem was the installation of tube-end sleeve. Last year, after removing 340 installed plugs from tubes, selected 269 tubes took tube-end sleeve installation. Tube-end sleeve brought pressure boundary from parent tube to installed sleeve tube. Tube-end sleeve has the benefit of reducing outage period and increasing more revenue than replacing S/G. This paper is provided to assist interest parties in effectively understanding this issue.