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CANDU형 원전 경년열화 감시시스템(Aging Monitor) 개발
김홍기,최영환,고한옥,Kim, Hong Key,Choi, Young Hwan,Ko, Han Ok 한국압력기기공학회 2009 한국압력기기공학회 논문집 Vol.5 No.2
As the operating time in nuclear power plants (NPPs) increases, the integrity of nuclear components may be continually degraded due to aging effects of systems, structures and components. Recently, a number of NPPs are being operated beyond their design life to produce more electricity without shutting down. The critical issue in extending a lifetime is to maintain the level of safety during the extended operation period while satisfying the international regulatory standards. Therefore, it is beneficial to build a monitoring system to measure an aging status. In this paper, the Aging Monitor (AM) based on lots of aging database obtained from the operating plants and research results on the aging effects was developed to monitor, manage and evaluate the aging phenomena systematically and effectively in NPPs. The AM for the CANDU is divided into 6 modules: (1) Aging Alarm/Coloring Monitor, (2) Aging Database, (3) Aging Document, (4) Real-time Integrity Monitor, (5) Surveillance and Inspection Management System, and (6) Continued Operation and Periodic Safety Review (PSR) Safety Evaluation. The proposed system is expected to provide the integrity assessment for the major mechanical components of an NPP under concurrent working environments.
김홍기,송명호,노승환,김세창,Kim, Hong Key,Song, Myung Ho,Nho, Seung Hwan,Kim, Se Chang 한국압력기기공학회 2011 한국압력기기공학회 논문집 Vol.7 No.4
As NPPs' operating times increase, the integrity of nuclear components is continually degraded due to aging effects of systems, structures and components. In addition, for the case of continued operation beyond design life, additional aging effects occurred during the extended operating period lead to more degradation of the integrity of nuclear components. Therefore, it is very important to mange and evaluate the aging to secure the safety of NPPs. Wolsong unit 1 is approaching to its design life of 30 years in 2012. The license renewal documents for continued operation of Wolsong unit 1 Is under reviewing now. In this paper, regulatory technologies for continued operation of Wolsong unit 1 developed by KINS will be introduced. That technologies include the safety review guidelines, regulatory guides for aging management program and regulatory program for audit calculation.
CANDU형 원전 경년열화 감시시스템(Aging Monitor) 개발
김홍기(Hong Key Kim),최영환(Young Hwan Choi),최재붕(Jae Boong Choi),고한옥(Han Ok Ko) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.5
As the operating time in nuclear power plants (NPPs) increases, the integrity of nuclear components may be continually degraded due to aging effects of systems, structures and components. Based on lots of aging database obtained from the operating plants and research results on the aging effects, the aging monitor (AM) was developed to monitor, manage and evaluate the aging phenomena systematically and effectively in NPPs. In this paper, the CANDU Aging Monitor for including 6 modules was introduced: (1) Aging Alarm/Coloring Monitor, (2) Aging Database, (3) Aging Document, (4) Real-time Integrity Monitor, (5) Surveillance and Inspection Management System, and (6) Continued Operation and Periodic Safety Review (PSR) Safety Evaluation.
월성1호기 계속운전 관련 결함연료위치탐지계통 배관의 열화관리평가
송명호,김홍기,이영호,Song, Myung Ho,Kim, Hong Key,Lee, Young Ho 한국압력기기공학회 2011 한국압력기기공학회 논문집 Vol.7 No.2
The end of design lifetime for Wolsong unit 1 will be reached on 20th November in 2012. So the license renewal documents for the continuous operation of Wolsong unit 1 is under reviewing now. Major components of primary system such as pressure tubes, feeder pipes including delayed neutron monitoring system tubing are being replaced and many components of secondary system are also being repaired. In this paper, the assessment on the wear degradation of delayed neutron monitoring system tubing(on the other hand, DN tube was called) was performed for the ageing management of the same component. The wear defects of this component was one of causes that resulted in heavy water leakage accidents. Therefore design specifications of Wolsong uint 1 and heavy water leakage accidents of pressurized heavy water reactors were reviewed and causes of wear defect for DN tubes were analyzed. Wear propagation equations based on the heavy water leakage history were made and the proper repairing time was possible to be expected if the continued operation was considered. Finally design change items of DN tubes that were conducted for the long term operation of Wolsong unit 1 are introduced.
송명호,김홍기,이정민,Song, Myung Ho,Kim, Hong Key,Lee, Jung Min 한국압력기기공학회 2010 한국압력기기공학회 논문집 Vol.6 No.2
As a part of license renewal for the continued operation of Wolsong unit 1, the periodic safety review report was submitted near the end of design lifetime, 2012, and now is under reviewing. Major components of primary system such as pressure tubes, feeder pipes and so on are being replaced and many components of secondary system are also being repaired. So the license renewal of Wolsong unit 1 is expected to be acquired without significant issues. But on the other hand, steam generators of Wolsong unit 1 had the good performance and therefore the replacement and repair for the steam generator are not needed. Recently it is reported that some cracks were detected in a few of european steam generator with Alloy 800 tubes and the cause of cracks was the outer diameter stress corrosion cracking(ODSCC) due to the concentration of chemical impurities on the outer surface of tube. Accordingly the overall review on this issue was performed. The long-term operation is likely to results to form the concentration mechanism for the tube corrosion as the sludge build-up in the secondary side of steam generator and the crack in the crevice between tube and tube-sheet and expansion transitions is apt to be occurred. In this paper, the history of steam generator inspection and operation of Wolsong unit 1 are reviewed and the reliability of steam generator tube is evaluated and the steam generator aging management program for Wolsong unit 1 is introduced.
CANDU형 원전 주요기기의 피로손상 평가를 위한 그린함수 개발
김세창,성희동,최재붕,김홍기,송명호,노승환,Kim, Se Chang,Sung, Hee Dong,Choi, Jae Boong,Kim, Hong Key,Song, Myung Ho,Nho, Seung Hwan 한국압력기기공학회 2011 한국압력기기공학회 논문집 Vol.7 No.4
For the efficient and safe operation of nuclear power plant, evaluating quantitatively aging phenomenon of major components is necessary. Especially, typical aging parameters such as stresses and cumulative usage factors should be determined accurately to manage the lifetime of the plant facility. The 3-D finite element(FE) model is generated to calculate the aging parameters. Mechanical and thermal transfer functions called Green's functions are developed for the FE model with standard step input. The stress results estimated from transfer functions are verified by comparing with 3-D FE analyses results. Lastly, we suggest an effective fatigue evaluation methodology by using the transfer functions. The usefulness of the proposed fatigue evaluation methodology can be maximized by combining it with an on-line monitoring system.
최영환(Young Hwan Choi),김홍기(Hong Key Kim) 대한기계학회 2010 大韓機械學會論文集A Vol.34 No.4
이 연구에서는 우리나라 CANDU형 원전의 계속운전 규제지침을 개발하였다. CANDU 600 로형인 월성 1호기는 2012년에 30년 설계수명에 도달한다. 설계수명이후에 계속운전을 원하는 원전 사업자는 11개 인자를 포함하는 주기적안전성 평가 보고서를 제출해야 하며, 추가로 다음 사항에 대한 보고서를 제출해야 한다. (1) 경년열화 관리에 대한 범위 및 사전 검토 결과 (2) 경년열화 관리 프로그램 (3) 계속 운전기간을 포함하는 시간제한 경년열화 수명평가, (4) 운전경험 및 주요 연구결과의 반영. 이 연구에서는 상기 항목에 대한 54개의 규제지침이 개발되었다. In this paper, the regulatory guidelines for the continued operation of the CANDU reactor in Korea were introduced. Wolsong Unit 1, which is a CANDU 600 reactor in Korea, will reach its design life of 30 years in 2012. A licensee who wants to operate a nuclear power plant beyond its design life should submit reports of periodic safety reviews (PSRs) conducted on the basis of 11 safety factors. In addition, the licensee should provide the following: (1) scoping and screening results for aging management, (2) aging management program, (3) TLAA, including the continued operation term, (4) operation-experience feedback, and (5) important safety-research results. In this study, 54 regulatory guidelines for the five above-mentioned items for the CANDU reactor in Korea were developed.
최영환(Young Hwan Choi),김홍기(Hong Key Kim) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.5
Regulatory guidelines for the continued operation of CANDU reactor in Korea were introduced in this paper. Wolsong unit 1, which is a CANDU 600 reactor in Korea, is approaching to its design life of 30 years in 2012. The licensee who wants to operate a nuclear power plant beyond its design life should submit the periodic safety review (PSR) report conducted based on the eleven safety factors. In addition, the licensee should provide the items as follows: (1) Scoping and screening results of aging management, (2) Aging management program, (3) TLAA including the continued operation term, and (4) Operation experience feedback and important safety research results. In this study, the 53 regulatory guidelines for the above 4 items for the CANDU reactor in Korea were developed.