• Title/Summary/Keyword: Primary Piping

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Material Noise Reduction in Ultrasonic Test Using Polarity Thresholding Algorithm (초음파탐상 수행시 Polarity Thresholding 알고리즘을 이용한 재료잡음 억제)

  • Koo, Kil-Mo;Ko, Dae-Sik;Kim, Tae-Hyoun;Jun, Kye-Suk
    • The Journal of the Acoustical Society of Korea
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    • v.14 no.1
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    • pp.73-80
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    • 1995
  • In this paper, Polarity Thresholding(PT) algorithm has been studied to enhance the received signal in ultrasonic inspection of the stainless-steel(SUS 304) which is the primary piping material of a nuclear power plant. The spectral decomposition components obtained by splitting the spectrum of received signals are composed of dispersive signal of the interference pattern produced by the grain boundaries and nondispersive signal by the flaw. PT algorithm enhance the SNR of received signal by using above properties. In experiment the stainless-steel has been chosen as the sample and heat-treated at 1125, 1150, 1175, and $1200^\circ{C}$, respectively. And the flat-bottom hole type defects have been made artificially in samples. The pulse-echo signals from the sample by using ultrasonic transducer of center frequency 5 MHz have been processed by PT algorithm. It has been shown that PT algorithm enhanced the SNR by average 14.2 dB.

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Tensile and impact toughness properties of various regions of dissimilar joints of nuclear grade steels

  • Karthick, K.;Malarvizhi, S.;Balasubramanian, V.;Krishnan, S.A.;Sasikala, G.;Albert, Shaju K.
    • Nuclear Engineering and Technology
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    • v.50 no.1
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    • pp.116-125
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    • 2018
  • Modified 9Cr-1Mo ferritic steel is a preferred material for steam generators in nuclear power plants for their creep strength and good corrosion resistance. Austenitic stainless steels, such as type 316LN, are used in the high temperature segments such as reactor pressure vessels and primary piping systems. So, the dissimilar joints between these materials are inevitable. In this investigation, dissimilar joints were fabricated by the Shielded Metal Arc Welding (SMAW) process with Inconel 82/182 filler metals. The notch tensile properties and Charpy V-notch impact toughness properties of various regions of dissimilar metal weld joints (DMWJs) were evaluated as per the standards. The microhardness distribution across the DMWJs was recorded. Microstructural features of different regions were characterized by optical and scanning electron microscopy. Inhomogeneous notch tensile properties were observed across the DMWJs. Impact toughness values of various regions of the DMWJs were slightly higher than the prescribed value. Formation of a carbon-enriched hard zone at the interface between the ferritic steel and the buttering material enhanced the notch tensile properties of the heat-affected-zone (HAZ) of P91. The complex microstructure developed at the interfaces of the DMWJs was the reason for inhomogeneous mechanical properties.

Failure Analysis of Welded type 304 in Cooling Water Pipeline of District Heating System (지역난방 냉각수 배관의 용접부 파손 분석)

  • Jeong, Joon-Cheol;Kim, Woo-Cheol;Kim, Kyung Min;Sohn, Hong-Kyun;Kim, Jung-Gu;Lee, Soo-Yeol;Kim, Heesan
    • Corrosion Science and Technology
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    • v.19 no.6
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    • pp.296-301
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    • 2020
  • Failure analysis on the welded type 304 pipe used for cooling water piping in the district heating primary side was conducted. Inorganic elements and bacteria in the cooling water and in corrosion products were analyzed, and the weldment was inspected by microscopy and a sensitization test. Corrosion damages were observed in the heat-affected zone, on weld defects such as incomplete fusion or excessive penetration caused by improper welding, or/and at the 6 o'clock position along the pipe axial direction. However, the level of concentration of chloride in the cooling water as low as 80 ppm has been reported to be not enough for even a sensitized type 304 steel, meaning that the additional corrosive factor was required for these corrosion damages. The factor leading to these corrosion damages was drawn to be the metabolisms of the types of bacteria, which is proved by the detection of proton, sulfur containing species, biofilms, and both bacteria and corrosion product analyses.

A Study on Weight Estimation and Calculation of the Pipe Rack Structures for FPSO EPC Projects (FPSO Topsides Pipe Rack 견적 중량 추산 방법 연구)

  • Lee, Soo-Ho;Ahn, Hyun-Sik;Kim, Han-sung;Heo, Yoon;Bae, Jae-Ryu;Kim, Ki-Su;Ham, Seung-Ho;Lee, Sung-Min;Roh, Myung-Il
    • Journal of the Society of Naval Architects of Korea
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    • v.53 no.5
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    • pp.362-370
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    • 2016
  • The weight estimation and calculation of FPSO topsides is first performed at the bidding stage of projects. At this time, it is difficult to estimate and calculate accurately the weight because most of items of FPSO are not apparently defined. Especially, in the case of the pipe rack module, its portion of the total weight and the range of weight variation are large due to special features of piping and electric equipment in the module. Thus, it is very important to estimate and calculate accurately its weight in the task of the weight estimation and calculation of FPSO topsides. In this study, the past data for the weight of the pipe rack module were collected and analyzed, the WBS (Work Breakdown Structure) for the pipe rack module was constructed, and primary variables and secondary variables for developing a weight estimation and calculation model were selected. That is, after analyzing the past data, the volume was selected as the primary variable and the regression analysis was performed based on the variable. Then, several secondary variables were selected and incorporated into a weight estimation and calculation model. At this time, the weight per discipline was assumed from ratios of the total weight. Finally, the weight of the pipe rack module was estimated and calculated by using the developed model. As a result, the deviation from the model was better than that (-20 % ~ 60 %) of other studies about the weight estimation and calculation of FPSO topsides. Thus, the validity and applicability of the weight estimation and calculation of the pipe rack could be checked.

Stress and Fatigue Evaluation of Distributor for Heat Recovery Steam Generator in Combined Cycle Power Plant (복합발전플랜트 배열회수보일러 분배기의 응력 및 피로 평가)

  • Lee, Boo-Youn
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.19 no.8
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    • pp.44-54
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    • 2018
  • Stress and fatigue of the distributor, an equipment of the high-pressure evaporator for the HRSG, were evaluated according to ASME Boiler & Pressure Vessel Code Section VIII Division 2. First, from the results of the piping system analysis model, reaction forces of the tubes connected to the distributor were derived and used as the nozzle load applied to the detailed analysis model of the distributor afterward. Next, the detailed model to analyze the distributor was constructed, the distributor being statically analyzed for the design condition with the steam pressure and the nozzle load. As a result, the maximum stress occurred at the bore of the horizontal nozzle, and the primary membrane stress at the shell and nozzle was found to be less than the allowable. Next, for the transient operating conditions given for the distributor, thermal analysis was performed and the structural analysis was carried out with the steam pressure, nozzle load, and thermal load. Under the transient conditions, the maximum stress occurred at the vertical downcomer nozzle, and of which fatigue life was evaluated. As a result, the cumulative usage factor was less than the allowable and hence the distributor was found to be safe from fatigue failure.