• Title/Summary/Keyword: Vessel inspection

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Selection of Measuring Sensors for Reactor Vessel Internals Comprehensive Vibration Assessment Program in Advanced Power Reactor 1400 (APR1400 원자로 내부구조물 종합진동평가 측정센서 선정)

  • Ko, Do-Young;Lee, Jae-Gon
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2010.10a
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    • pp.433-438
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    • 2010
  • Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. Nuclear Regulatory Commission Regulatory Guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement, and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors. We analyzed RVI design data of Palo Verde nuclear generating station(U.S.) and Yonggwang nuclear generating station(Korea) and investigated measuring sensors used in both of them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected the most suitable sensors for RVI CVAP in Advanced Power Reactor 1400(APR1400).

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Ultrasonic Phased Array Techniques for Detection of Flaws of Stud Bolts in Nuclear Power Plants

  • Lee, Joon-Hyun;Choi, Sang-Woo
    • Journal of the Korean Society for Nondestructive Testing
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    • v.26 no.6
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    • pp.440-446
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    • 2006
  • The reactor vessel body and closure head are fastened with the stud bolt that is one of crucial parts for safety of the reactor vessels in nuclear power plants. It is reported that the stud bolt is often experienced by fatigue cracks initiated at threads. Stud bolts are inspected by the ultrasonic technique during the overhaul periodically for the prevention of failure which leads to radioactive leakage from the nuclear reactor. The conventional ultrasonic inspection for stud bolts was mainly conducted by reflected echo method based on shadow effect. However, in this technique, there were numerous spurious signals reflected from every oblique surfaces of the thread. In this study, ultrasonic phased array technique was applied to investigate detectability of flaws in stud bolts and characteristics of ultrasonic images corresponding to different scanning methods, that is, sector and linear scan. For this purpose, simplified stud bolt specimens with artificial defects of various depths were prepared.

Selection Criteria of Measurement Locations for Advanced Power Reactor 1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program (APR1400 원자로내부구조물 종합진동평가 측정위치 선정 기준)

  • Ko, Do-Young;Kim, Kyu-Hyung;Kim, Sung-Hwan
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.21 no.8
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    • pp.708-713
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    • 2011
  • U.S. nuclear regulatory commission(NRC) regulatory guide(RG) 1.20 requires a comprehensive vibration assessment program(CVAP) for use in verifying the structural integrity of reactor vessel internals(RVI) for flow-induced vibrations prior to commercial operation. The CVAP program consist of vibration and fatigue analysis, a vibration measurement program, an inspection program, and a correlation of their results. One of the main purposes of the analysis program is to select measurement locations, however measurement locations can not be determined by only analysis results, therefore we developed selection criteria of measurement locations for advanced power reactor 1400(APR1400) RVI CVAP, It will be used to select measurement locations and instrument types for APR1400 RVI CVAP.

Design of Remotely Operated, Underwater Robotic Vehicle System for Reactor Vessel Inspection and Foreign Objects Removal (원자로 압력용기 육안검사 및 이물질 제거용 수중로봇 시스템의 설계)

  • 조병학;변승현;김진석;오정묵
    • Proceedings of the IEEK Conference
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    • 2002.06e
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    • pp.153-156
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    • 2002
  • The remotely operated underwater robotic vehicle system has been required to inspect some objects such as baffle former bolts and remove foreign objects in reactor vessel of nuclear power plant. In this paper, we have designed the remotely operated underwater robotic vehicle system that includes a long reach arm that is composed of 4 joints to remove foreign objects in a narrow space, a camera for visual test, instrument sensors for vehicle positioning, 4 thrusters for underwater navigation of vehicle, and supervisory control system implemented with industrial PC that includes robot simulator that has the functions of real time visualization, robot work planning and etc.

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Validation of Vibration and Stress Analysis Methodology for APR1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program (APR1400 원자로내부구조물 종합진동평가프로그램 진동 및 응력해석 방법론 검증)

  • Kim, Kyu Hyung;Ko, Do Young;Kim, Sung Hwan
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2012.10a
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    • pp.300-305
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    • 2012
  • The vibration and stress analysis program of comprehensive vibration assessment program (CVAP) is to verify theoretically the structural integrity of reactor vessel internals (RVI) and to provide the basis for selecting the locations monitored in measurement and inspection programs. This paper covers the verification of the vibration and stress analysis methodology of APR1400 RVI CVAP. The analysis methodology was developed to use 3-dimensional hydraulic and structural models with ANSYS and CFX. To validate the methodology, the hydraulic loads and structural reponses of OPR1000 were predicted and compared with the calculated and measured data in the OPR1000 RVI CVAP. Since the results predicted with this methodology were close to the measured values considerably, it was confirmed that the analysis methodology was developed properly.

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Reactor vessel head penetration J-groove welds inspection by TOFD technique (TOFD Technique을 이용한 원자로헤드 관통관 용접부 비파괴검사)

  • Kim, Wang-Bae;Lee, Yeong-Ho;Mun, Yong-Sik;Kim, Chang-Su
    • Proceedings of the KWS Conference
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    • 2005.06a
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    • pp.185-187
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    • 2005
  • The reactor pressure vessel head of PWR has penetrations for control rod drive mechanism and instrumentation systems. The Primary coolant water and operating temperature can cause the stress-corrosion cracking of these nickel-based alloy penetrations. It is difficult to detect and size flaws such as SCC in the reactor head penetrations using conventional W methods because of complex geometry, Therefore, the utilities are using the TOFD technique for the detection and sizing of the flaw. This study shows the correlation between the ultrasonic wave direction and the orientation of the flaw and the range of flaw depth which can be detected by the TOFD techniques.

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A Clinical Study of Correlation Between Frequently Occurring Headache from Gastrointestinal Disorder and Dyspepsia (소화불량증에서 호발하는 두통의 위장질환과의 상관성에 대한 임상연구)

  • Choi, Young-Gyoo;Kim, Jae-Kwan;Choi, Seo-Hyung
    • The Journal of the Society of Korean Medicine Diagnostics
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    • v.14 no.1
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    • pp.36-43
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    • 2010
  • Objectives: Since we found patients with dyspepsia as their major symptom had high rate of headache, would like to find out a rational diagnosis ground by using EAV correlation between headache and gastrointestinal disorder Methods: We did survey and EAV inspection on 128 patients came by gastrointestinal disorder who quoted 4 and 5 degree for their headache symptoms) Results & Conclusion The results of this study were as follows: 1. From dyspepsia, we saw higher rate by order of epigastric discomfort, bloating, stomach trouble, bleching, etc. 2. By EAV analysis, found functional deterioration by order of stomach, nerval degeneration vessel, gall bladder/bile duct, liver. 3. By EAV analysis, functional deterioration of stomach, gall bladder/bile duct, liver represent dyspepsia and nerval degeneration vessel represent headache. We found the correlation between dyspepsia and headache by observation at a time.

An Experimental Study on the Resistance Performance of Small Size Fishing Vessel (소형 연안어선의 저항성능에 관한 실험적 연구)

  • Kim, Do-Jung;Park, Je-Woong;Kim, Ju-Nam;Jeong, Uh-Cheul
    • Journal of the Korean Society of Fisheries and Ocean Technology
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    • v.40 no.4
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    • pp.304-310
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    • 2004
  • Resistance performance of small size fishing vessel is experimentally investigated to find out the effect of fore-body shape and trim for the better hull from development. The tests are performed for five different cases in the high speed circulating water channel(CWC). Wave patterns are observed to investigate the relation between the resistance performance and the wave characteristics.

Accuracy of Ultrasonic Flaw Sizing using DAC Techniques for Pressure Vessels Welds of Nuclear Power Plant (초음파 DAC 기법을 이용한 압력용기 용접부의 지시 크기측정 정확도 평가)

  • Kim, Jae Dong;Lim, Hyung Taik;Doh, Eui Soon
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.2
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    • pp.20-24
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    • 2015
  • During refueling Outage, In-service inspections(ISIs) for the Nuclear Power Plant components are mandatory requirement in accordance with ASME Code Sec. XI. Especially, in current ultrasonic testing is one of the most important NDT techniques that are used for volumetric examination methods for nuclear power plant components, and accurate sizing of flaw indication by UT is essential to assure the integrity of the components. However, ASME code specifies minimum requirement for vessel examination procedure, and so far many different flaw sizing approaches have been tried to apply. Through the Round Robin Test(RRT), the accuracy of ultrasonic flaw sizing using DAC techniques was measured with the mock-ups simulating typical pressure vessel welds. These mock-ups contain artificially introduced flaws of known size and location. This paper shows experimental comparison data on the accuracy of techniques using such as 6dB drop, 50%DAC, 20%DAC and 20%DAC with beam spread correction, and also shows that diverse DAC techniques can be effectively applied to the assessment of the flaw sizing for pressure vessel welds in the stage of welding and fabrication.

Measurement of Thickness and Position of the Surface using the Two Encoder Ultrasonic Sensors (두개의 엔코드 초음파 센서를 이용한 측정면의 두께 측정 및 위치 측정)

  • 강명철;장유신;김형국;배종일;이만형
    • Proceedings of the Korean Society of Machine Tool Engineers Conference
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    • 2002.04a
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    • pp.510-514
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    • 2002
  • The 3-dimensional measuring machine by using an ultrasonic sensor is used one of the NDE(Non Destructive Examination). It is applied to the inspection of pipelines, boreholes, pressure vessel and tank, and so on. In particular when a harsh environment prohibits the use of moving mechanical parts. The 3-dimensional measuring machine by using an ultrasonic sensor, which measure 1-dimensional information and 2-dimensional information simultaneously from a target of inspection, and then reembody 3-dimensional information. So we can find the situation in progress and predict remaining life and corrosion without destructive examination. It's a point of excellence that the 3-dimensional measuring machine is portable.

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