• Title/Summary/Keyword: thickness thinning

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Development of Numerical Algorithm of Total Point Method for Thinning Evaluation of Nuclear Secondary Pipes (원전 2차측 배관 감육여부 판별을 위한 Total Point Method 전산 알고리즘 개발)

  • Oh, Young Jin;Yun, Hun;Moon, Seung Jae;Han, Kyunghee;Park, Byeong Uk
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.2
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    • pp.31-39
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    • 2015
  • Pipe wall-thinning by flow-accelerated corrosion (FAC) and various types of erosion is a significant and costly damage phenomenon in secondary piping systems of nuclear power plants (NPPs). Most NPPs have management programs to ensure pipe integrity due to wall-thinning that includes periodic measurements for pipe wall thicknesses using ultrasonic tests (UTs). Nevertheless, thinning evaluations are not easy because the amount of thickness reduction being measured is often quite small compared to the accuracy of the inspection technique. U.S. Electric Power Research Institute (EPRI) had proposed Total Point Method (TPM) as a thinning occurrence evaluation method, which is a very useful method for detecting locally thinned pipes or fittings. However, evaluation engineers have to discern manually the measurement data because there are no numerical algorithm for TPM. In this study, numerical algorithms were developed based on non-parametric and parametric statistical method.

Application of Laser Ultrasonic Technique for Nondestructive Evaluation of Wall Thinning in Pipe (배관부 감육 손상의 비파괴 평가를 위한 레이저 초음파 기술 적용)

  • Hong, Kyung-Min;Kang, Young-June;Park, Nak-Kyu;Yoon, Suk-Bum
    • Journal of the Korean Society for Nondestructive Testing
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    • v.33 no.4
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    • pp.361-367
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    • 2013
  • Many of the nuclear power plant pipe is used in high temperature and high pressure environment. Wall thinning frequently caused by the corrosion. These wall thinning in pipe is expected gradually increase as nuclear power become superannuated. Therefore there is need to evaluate wall thinning in pipe and corrosion defect by non-destructive method to prevent the accident of the nuclear power facility due to pipe corrosion. Especially for real-time assessment of the wall thinning that occurs in nuclear power plant pipe, the laser ultrasonic technology can be measured even in hard-to-reach areas, beyond the limits of earlier existing contact methods. In this study, the optical method using laser was applied for non-destructive and non-contact evaluation. Ultrasonic signals was acquired through generating ultrasonic by pulse laser and using laser interferometer. First the ultrasonic signal was detected in no wall thinning in pipe, then a longitudinal wave velocity was measured inside of pipe. Artificial wall thinning specimen compared to 20, 30, 40 and 50% of thickness of the pipe was produced and the longitudinal wave velocity was measured. It was possible to evaluate quantitatively the wall thinning area(internal defect depth) cause it was able to calculate the thickness of each specimen using measured longitudinal wave velocity.

A Study on Failure Mode of Pipe Elbows with Wall Thinning (두께 감소된 배관 엘보우의 파손 모드에 대한 연구)

  • Shin, Kyu-In;Yoon, Kee-Bong
    • Journal of the Korean Institute of Gas
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    • v.12 no.2
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    • pp.57-62
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    • 2008
  • Difference of failure modes was studied by finite element analysis for elbows with local wall thinning area particularly at inner surface of intrados of the elbow. Longitudinal wall thinning length, minimum thickness were kept constant but circumferential wall thinning width was varied to get $90^{\circ}$, $180^{\circ}$ and $360^{\circ}$ thinning width. Elastic-plastic analysis were carried out under the combined loading conditions of internal pressure and in-plane bending moment closing the elbow. Von Mises stress were obtained from the outer surface central surface location in intrados, extrados and crown parts in elbow. The results showed that the plastic deformation and failure started from the crown location when the thinning width small ($90{\sim}180^{\circ}$). However, plastic collapse started from the intrados location when the thinning width is approaching $360^{\circ}C$. This should be reflected to assess structural integrity of elbows after wall thinning measurement is made.

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Technology Based on Wall-Thinning Prediction and Numerical Analysis Techniques for Wall-Thinning Analysis of Small-Bore Carbon Steel Piping (감육예측 및 수치해석 기법을 활용한 소구경 탄소강배관 감육영향 분석에 관한 연구)

  • Lee, Dae-Young;Hwang, Kyeong-Mo;Jin, Tae-Eun;Park, Won;Oh, Dong-Hoon
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.34 no.4
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    • pp.429-435
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    • 2010
  • In approximately fifty utilities, including KHNP (Korea Hydro & Nuclear Power), CHECWORKS is used as a tool for predicting and managing the wall thinning of carbon steel piping; this wall thinning is caused by flow-accelerated corrosion (FAC). It is known that CHECWORKS is only applicable to predict the wall thinning of piping with large bores. When dealing with small-bore steel piping, FAC engineers measure the thickness of the susceptible area that is selected on the basis of the experience and judgment of the engineer. This paper proposes the application of CHECWORKS for the management of wall thinning of small-bore piping. Four small-bore pipelines of a domestic nuclear power plant were analyzed from the viewpoints of FAC and fluid dynamics by using CHECWORKS and FLUENT code. Depending on the engineer's skill, CHECWORKS can also be used for the management of wall thinning of small-bore piping.

Cause Analysis for the Wall Thinning and Leakage of a Small Bore Piping Downstream of an Orifice (주증기계통 오리피스 후단 소구경 배관의 감육 및 누설 발생)

  • Hwang, Kyeong Mo
    • Corrosion Science and Technology
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    • v.12 no.5
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    • pp.227-232
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    • 2013
  • A number of components installed in the secondary system of nuclear power plants are exposed to aging mechanisms such as FAC (Flow-Accelerated Corrosion), Cavitation, Flashing, and LDIE (Liquid Droplet Impingement Erosion). Those aging mechanisms can lead to thinning of the components. In April 2013, one (1) inch small bore piping branched from the main steam line experienced leakage resulting from wall thinning in a 1,000 MWe Korean PWR nuclear power plant. During the normal operation, extracted steam from the main steam line goes to condenser through the small bore piping. The leak occurred in the downstream of an orifice. A control valve with vertical flow path was placed on in front of the orifice. This paper deals with UT (Ultrasonic Test) thickness data, SEM images, and numerical simulation results in order to analyze the extent of damage and the cause of leakage in the small bore piping. As a result, it is concluded that the main cause of the small bore pipe wall thinning is liquid droplet impingement erosion. Moreover, it is observed that the leak occurred at the reattachment point of the vortex flow in the downstream side of the orifice.

THE COMPARATIVE STUDY OF ROOT COVERAGE EFFECT OF DIFFERENT CONNECTIVE TISSUE OBTAINING METHODS (결합조직 채득방법에 따른 치은퇴축 회복의 비교연구)

  • Choi, Yong-Suk;Yim, Sung-Bin;Chung, Chin-Hyung
    • Journal of Periodontal and Implant Science
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    • v.25 no.1
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    • pp.146-152
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    • 1995
  • A mucogingival grafting procedure has been developed to cover denuded root surfaces. The subepithelial connective tissue graft is composed of a free connective tissue graft and an overlying pedicle graft. The source of connective tissue graft were trap door approach and thining of a full thickness palatal flap. The purpose of this study was compare a two different connective tissue obtaining method. In this study, where palatal pocket was present, pocket elimination was performed, and the tissue normally discarded after thinning of the palatal flap was used as a grafting material. The results were as follows : 1. The mean difference between trap door approach and thinning procedure for root coverage were $2.1{\pm}O.lmm$, $2.2{\pm}O.2mm$. 2. The mean difference between trap door approach and thinning procedure for pocket depth change were $O.2{\pm}O.lmm$, $O.2{\pm}O.2mm$. 3. The mean difference between trap door approach and thinning procedure for attachment gain were $2.1{\pm}O.2mm$, $2.4{\pm}O.2mm$. 4. The esthetics in recipient site, both color match and tissue contour, were acceptable to the patient in all cases. 5. Therefore, thinning procedure were similar to trap door approach in root coverage effect.

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A Study on Experiment and Numerical Analysis for Disclosing Shell Wall Thinning of a Feedwater Heater (급수가열기 추기노즐 충격판 주변의 동체감육 현상규명을 위한 실험 및 수치해석 연구)

  • Kim, Kyung-Hoon;Lee, Woo;Hwang, Kyeong-Mo
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.31 no.1 s.256
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    • pp.1-7
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    • 2007
  • Feedwater heaters of many nuclear power plants have recently experienced severe wall thinning damage, which will increase as operating time progresses. Several nuclear power plants in Korea have experienced wall thinning damage in the area around the impingement baffle - installed downstream of the high pressure turbine extraction steam line - inside number 5A and 5B feedwater heaters. At that point, the extracted steam from the high pressure turbine is two phase fluid at high temperature, high pressure, and high speed. Since it flows in reverse direction after impinging the impingement baffle, the shell wall of the number 5 high pressure feedwater heater may be affected by flow-accelerated corrosion. This paper describes the comparisons between the numerical analysis results using the FLUENT code and the down scale experimental data in an effort to determine root causes of the shell wall thinning of the high pressure feedwater heaters. The numerical analysis and experimental data were also confirmed by actual wall thickness measured by an ultrasonic test.

A Study on the Fluid Mixing Analysis for Proving Shell Wall Thinning of a Feedwater Heater (급수가열기 동체 감육 현상 규명을 위한 유동해석 연구)

  • Kim, Kyung-Hoon;Hwang, Kyeong-Mo;Kim, Sang-Nyung
    • Journal of ILASS-Korea
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    • v.9 no.4
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    • pp.24-30
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    • 2004
  • Feedwater flowing tube side of number 5 high pressure feedwatrr heaters was heated by extracting steam from high pressure turbine and draining water from moisture separators and number 6 high pressure feedwater heaters and supplied into steam generators. Because the extracting steam from the high pressure turbine is two phase fluid of high temperature, high pressure, and high speed and flows to inverse direction after impinging to impingement baffle. the shell wall of the number 5 high pressure feedwater heater may be affected by flow accelerated corrosion. On May 14, 1999, Point Beach Nuclear Plant (PBNP) with operating at full power experienced a steam leak from rupture of shell side of number 4B feedwater heater. Also, d domestic nuclear power plant experienced a severe wall thinning of shell side of number 5A and 5B feedwater heaters. This paper describes the fluid mixing analysis study using PHOENICS code in order to get at the root of the shell wall thinning of the feedwater heaters. The sections included in the fluid mixing analysis model are around the number 5h feedwater heater shell including the extracting pipeline. To identify the relation between the local velocities and wall thinning. the local velocities according to the analysis results were compared with the distribution of the shell wall thickness by ultrasonic test.

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Experimental Study on Non-Axisymmetric Rectangular Cup using Multi-Stage Deep Drawing Process (직사각 컵 성형을 위한 다단 디프드로잉 공정의 실험적 연구)

  • Ku, T.W.;Park, J.W.;Heo, S.C.;Kang, B.S.
    • Transactions of Materials Processing
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    • v.19 no.4
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    • pp.253-262
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    • 2010
  • For multi-stage deep drawing process including ironing operation and biaxial forming in this study, tool developments are achieved, and the developed tool sets are applied to experimental investigations. In process and tool designs, a contact condition between intermediate blank and lower die is considered as the sequential one. In this study, the material used is cold-rolled thin sheet (SPCE) with the initial thickness of 0.4mm. From the experimental approaches, several failures such as tearing, localized thickening and thinning, are observed. To solve these failures, the contact surface on the lower die is modified. As the experimental results by applying the modified lower die, it is investigated that the failures are not occurred, and the excessive deformation behavior due to the thinning and thickening effects are decreased. Furthermore, the thickness distributions on the major axis and the minor axis of each intermediate blank are investigated to be already satisfied the target (ironing) thickness, respectively. By this systematic approach, it is confirmed that the experimental results show good agreements with the designed and required configuration of each deformed and final products.

Thinning of SDB SOI by electrochemical etch-stop (전기화학적 식각정지에 의한 SDB SOI의 박막화)

  • Chung, Yun-Sik;Chung, Gwiy-Sang
    • Proceedings of the KIEE Conference
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    • 2001.07c
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    • pp.1369-1371
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    • 2001
  • This paper describes on thinning SDB SOI substrates by SDB technology and Electro-chemical etch-stop. The surface of the fabricated SDB SOI substrates is more uniform than that grinding or polishing by mechanical method, and this process is possible to accurate SOI thickness control. During Electrochemical etch-stop, leakage current versus voltage curves were measured for analysis of the open current potential (OCP) point and the passivation potential (PP) poin and determinated to anodic passivation potential. The surface roughness and selectively controlled thickness of the fabricated SOI substrates were analyzed by using AFM and SEM, respectively.

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