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가압기 전열기 슬리브 및 J-Groove 용접부의 자동 초음파검사
류승우,장희준,김선제,이상덕,성종환,Ryu, Sung Woo,Chang, Hee Jun,Kim, Sun Je,Lee, Sang Duck,Sung, Jong Hwan 한국압력기기공학회 2010 한국압력기기공학회 논문집 Vol.6 No.2
In order to prevent the corrosion of component contacted primary water designed alloy 600 material in the nuclear power plant. But the primary water stress corrosion cracking(PWSCC) of alloy 600 and weld area occurs continuously due to the residual stress. The leakage accident resulted from PWSCC in the drain nozzle of the steam generator of domestic power plants. Heater sleeves of the pressurizer are welded with alloy 600 weld material and therefore exposed to the primary water environment. PWSCC occurred in heater sleeve material and weld area of many foreign power plants. The current issue of domestic nuclear power plants are consequently concentrated to PWSCC of similar material. In order to improve the detection and the sizing of the PWSCC in the welding sleeve of the pressurizer, the automatic UT system and multi-directions probe sets have been developed. The experimental studies have been performed using the mock-up block containing artificial reflectors(ID connected EDM notch) and semi-artificial cracks made from thermal fatigue. The automatic UT System is applied in the detection and the length sizing of the ID/OD on the tube and the J-groove weld area of the artificial reflectors and results of the detection and the sizing are compared respectively. Also, the developed automatic UT system is successfully accomplished to inspect the heater sleeve and the J-groove weld area on the pressurizer for the detection of PWSCC.
원자력발전 고방사선구역 소구경 노즐에 대한 자동화검사 기술
류승우(Sung Woo Ryu),윤기봉(Kee Bong Yoon),전규민(Gyu Min Jeon),성운학(Un Hak Seong) 한국비파괴검사학회 2016 한국비파괴검사학회지 Vol.36 No.6
원자력발전소의 노후화에 따른 이종금속용접부에서 결함 발생 사례가 지속적으로 보고되고 있으며, 국내에서도 원자력발전소 가동연수 증가에 따라 이종금속부에 결함 발생도 점점 증가할 것으로 판단된다. 국내에서는 증기발생기 배수 노즐 이종금속용접부, 원자로냉각재계통(RCS) 고온관 시료 채취 노즐에서 결함사례가 보고되었고, 원자력발전소의 인력 접근이 제한적인 고방사선구역 내 소구경 노즐의 이종금속용접부에 대한 검사 시 인력 투입을 최소화 하는 신뢰성 있는 자동화 비파괴검사 가능 기술 및 시스템 개발 필요성이 증대되고 있다. 본 연구에서는 원자력발전소의 소구경 노즐 결함 검출을 위해 1) beam simulation을 통한 최적 검사 탐촉자 설계, 2) 소구경 이종용접부 검사용 multi-directions UT 최적 검사기술, 3) 원격제어 automatic inspection system을 개발하였으며, 표준결함시편을 이용하여 개발된 기술 및 시스템의 결함 검출능을 검증하였다. 개발된 최적기술과 시스템은 실제 발전소에서 발생된 결함 (RCS 고온관 시료 채취 노즐)에 대한 검사에 적용하여 결함을 검출함으로써 개발 검사 기술 및 시스템의 적합성이 검증되었다. 개발된 기술은 원전의 다양한 소구경 건전성 평가에 활용함으로써 원자력발전 안전성 확보에 기여할 수 있을 것으로 기대된다. Defects in dissimilar metal welds are reported to be on the increase during the operating lifespan and aging of nuclear power plants. In Korea, reported cases of defects due to dissimilar metal welds include the drain nozzle of a steam generator and RCS hot tube sampling nozzles. Therefore, there is an urgent need to develop a reliable automated nondestructive inspection technique and a system for the inspection of dissimilar metal welds of small diameter nozzles in a high radiation area of a nuclear power plant. In this study, to ensure effective defect inspection of small diameter nozzles (RCS high-temperature tube sampling nozzle) of a nuclear power plant, three different methods were developed. These include: (1) optimum inspection probe design by beam simulation, (2) multi-directions UT optimum inspection technique for the inspection of small diameters of different welded parts, and (3) remote control automatic inspection system. The developed technique and systems have been verified to be suitable for use in the inspection of defects in smaller diameter nozzles in nuclear power plants.
사용후핵연료 핵분열생성물 누출탐상 Sipping 검사기술
신중철,양종대,성운학,류승우,박영우,Shin, Jung Cheol,Yang, Jong Dae,Sung, Un Hak,Ryu, Sung Woo,Park, Young Woo 한국압력기기공학회 2020 한국압력기기공학회 논문집 Vol.16 No.2
When a damage occurs in the nuclear fuel burning in the reactor, fission products that should be in the nuclear fuel rod are released into the reactor coolant. In this case, sipping test, a series of non-destructive inspection methods, are used to find leakage in nuclear fuel assemblies during the power plant overhaul period. In addition, the sipping test is also used to check the integrity of the spent fuel for moving to an intermediate dry storage, which is carried out as the first step of nuclear decommissioning, . In this paper, the principle and characteristics of the sipping test are described. The structure of the sipping inspection equipment is largely divided into a suction device that collects fissile material emitted from a damaged assembly and an analysis device that analyzes their nuclides. In order to make good use of the sipping technology, the radioactive level behavior of the primary system coolant and major damage mechanisms in the event of nuclear fuel damage are also introduced. This will be a reference for selecting an appropriate sipping method when dismantling a nuclear power plant in the future.
Boiler Feed-water Pump Turbine Rotor PAUT 자동화 탐상 장치 및 기법 개발
신중철(Jung Cheol Shin),박영우(Young Woo Park),류승우(Sung Woo Ryu),김준영(Chun Young Kim) 한국비파괴검사학회 2020 한국비파괴검사학회지 Vol.40 No.3
화력발전 BFPT 로터는 보일러 주급수 펌프 터빈의 중요 부품으로 가혹한 운전 환경에서 초고속으로 운전됨에 따라 고응력 부위인 휠과 버켓 도브테일에서 다양한 형태의 결함 발생 가능성이 높다. BFPT 로터의 휠과 버켓의 조립 형태는 Tangential 및 Axial로 구성되며, 선진 기업들만이 이들의 설계 및 제조 기술을 보유함에 따라 세부 사양과 형상이 공개되지 않아 정밀 비파괴검사 수행이 난해하였다. 본 연구는 국내 운전 중인 화력발전 BFPT 로터에 대해 역설계를 통해 형상 정보를 확보하였고, 목업 시편 제작, 최적 탐상용 PAUT 탐촉자 및 탐상 장치를 제작하여 휠과 버켓 도브테일에 대한 초음파 탐상기법 및 자동화 탐상 장치를 개발하였다. 본 연구를 통해 개발된 탐상기법과 자동화 탐상 장치는 화력 발전소의 BFPT 로터 가동중검사에 적용하여 발전 설비 운영의 안전성과 신뢰성을 제고하고자 한다. Boiler Feed-water Pump Turbine (BFPT) rotor is an important part of a boiler feed-water pump turbine in thermal power plants. It is operated at high speeds in severe operating environments. Furthermore, various types of defects can occur in high stress areas such as the bucket and wheel dovetail of the BFPT rotor. The assembly type of the wheel and bucket of the BFPT rotor comprises tangential and axial assemblies. As the design and manufacturing technology are owned by advanced technology companies, precise non-destructive testing is difficult because specifications and shapes are not disclosed. This paper presents the shape information via the reverse design of a BFPT rotor, which is in operation in Korea. Furthermore, a mockup, an optimum PAUT probe, defect detection technology, and automated scanning device for the wheel and bucket dovetail are manufactured. The defect detection method and automated scanning device developed in this study are applied to the rotor in-service inspection of thermal power plants for improving the safety and reliability of power plant operations. Hence, the purpose of the study is to improve the safety and reliability of power plant operations by applying the developed defect detection technology and automated scanning device for the BFPT rotor in-service inspection of power plants.