• Title/Summary/Keyword: water corrosion

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Root Cause Analysis and Structural Integrity Evaluation for a Crack in a Reactor Vessel Upper Head Penetration Nozzle (원자로 상부헤드 관통노즐 균열에 대한 원인분석 및 건전성 평가)

  • Lee, Kyoung-Soo;Lee, Sung-Ho;Lee, Jeong-Seog;Lee, Jae-Gon;Lee, Seung-Gun
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.9 no.1
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    • pp.56-61
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    • 2013
  • This paper presents the results of integrity assessment for the cracks happened in reactor vessel upper head penetration nozzles. The crack morphology for a boat sample from crack area was analyzed through microscope. The stress condition including weld residual stress around crack was analyzed using finite element analysis. From the results of crack morphology and stress condition, the crack was concluded as primary water stress corrosion cracking. The integrity of the cracked nozzle was assessed by the methodology provided in ASME Section XI. According to the assessment results, the remaining life of the cracked nozzle was 1.43 yrs. and the plant decided to repair it.

Operation Characteristics of the SBR Process with Electro-Flotation (EF) as Solids-liquid Separation Method (전해부상을 고액분리 방법으로 적용한 SBR 공정의 운전 특성)

  • Park, Minjeong;Choi, Younggyun
    • Journal of Korean Society on Water Environment
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    • v.24 no.3
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    • pp.340-344
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    • 2008
  • Electro-flotation (EF) was applied to a sequencing batch reactor process (SBR) in order to enhance solids-liquid separation. Solids-liquid separation was good enough in the SBR coupled with EF (EF-SBR) and it was possible to maintain the concentration of mixed liquor suspended solids (MLSS) high in the EF-SBR. Under moderate organic loading condition (COD loading rate: 6 g/day), control SBR (C-SBR) showed similar treatment efficiencies with the EF-SBR. Under high organic loading condition (COD loading rate: 9.6 g/day), the solids-liquid separation in the C-SBR was deteriorated due to proliferation of filamentous bulking organisms at high F/M ratio. However, the EF-SBR was operated stably and with the high MLSS concentration (above 4,000 mg/L) regardless of the organic loading conditions during overall operating period leading to the satisfactory effluent quality. Gas production rate of the electrodes was gradually decreased because of anodic corrosion and scale build-up at the surface of cathode. However it could be partially overcome by use of corrosion-proof electrode material (SUS-316 L) and by periodic current switching between the electrodes.

A Study on the Wall Thinning Range according to modified Extraction Nozzle Design in High Pressure Feedwater Heater (고압 급수가열기 추기노즐 설계변경에 따른 감육 범위 연구)

  • Park, Sang-Hoon;Yoo, Il-Gon;Kim, Kyung-Hoon;Hwang, Kyeong-Mo
    • Proceedings of the SAREK Conference
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    • 2009.06a
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    • pp.847-852
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    • 2009
  • Feedwater heaters of many nuclear power plants have recently experienced severe wall thinning damange, 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 inside feed-water heater installed downstream of the turbine extraction stream line. At that point, the extract steam from the turbine is two phase fluid at high temperature, high pressure, and high speed. Since it flows to reverse direction after impinging the impingement baffle, the shell wall of feedwater heaters may be affected by flow-accelerated corrosion. In this paper, to compare wall thinning range according to change entrance nozzle diameter and position with reference numerical analysis model's wall thinning range, various numerical analysis models applied. In case of changing diameter, four different diameter is applied. And a side of nozzle position, two different position-vertical type and parallel type-is applied. And then this paper describes operation of numerical analysis which is composed similar condition with real feed water heater. In conclusion, this study shows effective design for shall wall thinning by changing nozzle diameter and position.

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Prediction of Welding Residual Stress of Dissimilar Metal Weld of Nozzle using Finite Element Analyses (유한요소해석을 이용한 노즐 이종금속용접부의 용접잔류응력 예측)

  • Huh, Nam-Su;Kim, Jong-Wook;Choi, Suhn;Kim, Tae-Wan
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.83-84
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    • 2008
  • The primary water stress corrosion cracking (PWSCC) of dissimilar metal weld based on Alloy 82/182 is one of major issues in material degradation of nuclear components. It is well known that the crack initiation and growth due to PWSCC is influenced by material's susceptibility to PWSCC and distribution of welding residual stress. Therefore, modeling the welding residual stress is of interest in understanding crack formation and growth in dissimilar metal weld. Currently in Korea, a numerical round robin study is undertaken to provide guidance on the welding residual stress analysis of dissimilar metal weld. As a part of this effort, the present paper investigates distribution of welding resisual stress of a ferritic low alloy steel nozzle with dissimilar metal weld using Alloy 82/182. Two-dimensional thermo-mechanical finite element analyses are carried out to simulate multi-pass welding process on the basis of the detailed design and fabrication data. The present results are compared with those from other participants, and more works incorporating physical measurements are going to be performed to quantify the uncertainties relating to modelling assumptions.

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In situ synthesis of acrylic emulsion for improvement of anti corrosion property on steel plate (금속 코팅용 아크릴 올리고머 에멀젼의 합성에 관한 연구)

  • Lee, Soo;Park, Keun-Ho;Jin, Seok-Hwan;Park, Shin-Kyu
    • Journal of the Korean Applied Science and Technology
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    • v.25 no.4
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    • pp.485-494
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    • 2008
  • The acrylic coating emulsions were prepared by the emulsion polymerization to protect the surface of steel plate from the corrosion chemicals like acid, base and salt water. MMA(methyl methacrylate), styrene, BA(butyl acrylate), and 2-HEMA(2-hydroxyethyl methacrylate) were used as monomer. KPS(potassium persulfate) and SBS(sodium bisulfite) as redox initiator and SDBS(sodium dodecylbenzene sulfonate) as emulsifier were used on the emulsion polymerization reaction. The most stable in-situ coating was obtained when 10% of MMA was added. Both particle size and quantity in emulsion were decreased as increasing the mount of SDBS. the most stable prepared coating emulsion with polyisocyanate crosslinker showed very high anticorrosion properties on the coated steel layer to salt water, whereas no significant improvement of anticorrosion property to acdic and basic condition it showed.

Failure Analysis of Top Nozzle Holddown Spring Screw for Nuclear Fuel Assembly (핵연료상단고정체 누름스프링 체결나사의 파손해석)

  • Koh, S.K.;Ryu, C.H.;Lee, Jeong-Jun;Na, E.G.;Baek, T.H.;Jeon, K.L.
    • Proceedings of the KSME Conference
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    • 2003.11a
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    • pp.1234-1239
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    • 2003
  • A failure analysis of holddown spring screw was performed using fracture mechanics approach. The spring screw was designed such that it was capable of sustaining the loads imposed by the initial tensile preload and operational loads. In order to investigate the cause of failure, a stress analysis of the top nozzle spring assembly was done using finite element analysis and a life prediction of the screw was made using a fracture mechanics approach. The elastic-plastic finite element analysis showed that the local stresses at the critical regions of head-shank fillet and thread root significantly exceeded than the yield strength of the screw material, resulting in local plastic deformation. Primary water stress corrosion cracking life of the Inconel 600 screw was predicted by using integration of the Scott model and resulted in 1.42 years, which was fairly close to the actual service life of the holddown spring screw.

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A Study of Residual Stress Measurement in the Weld of Nuclear Materials (원전재료 모재 및 용접부 잔류응력측정 연구)

  • Lee, Kyoung-Soo;Lee, Jeong-Keun;Lee, Seong-Ho;Park, Jae-Hak
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.7 no.1
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    • pp.9-16
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    • 2011
  • Primary water stress corrosion cracking (PWSCC) has been found in the weld region of the nuclear power plant. Welding can produce tensile residual stress. Tensile residual stress contributes to the initiation and growth of PWSCC. It is important to estimate weld residual stress accurately to predict or prevent the initiation and growth of PWSCC. This paper shows the results of finite element analysis and measurement experiment for weld residual stress. For the study, four kinds of specimen were fabricated with the materials used in the nuclear power plant. Residual stresses were measured by four kinds of methods of hole drilling, x-ray diffraction, instrumented indentation and sectioning. Through the study, numerical analysis and measurement results were compared and the characteristics of each measurement technique were observed.

ROLE OF GRAIN BOUNDARY CARBIDES IN CRACKING BEHAVIOR OF Ni BASE ALLOYS

  • Hwang, Seong Sik;Lim, Yun Soo;Kim, Sung Woo;Kim, Dong Jin;Kim, Hong Pyo
    • Nuclear Engineering and Technology
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    • v.45 no.1
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    • pp.73-80
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    • 2013
  • The primary water stress corrosion cracking (PWSCC) of Alloy 600 in a PWR has been reported in the control rod drive mechanism (CRDM), pressurizer instrumentation, and the pressurizer heater sleeves. Recently, two cases of boric acid precipitation that indicated leaking of the primary cooling water were reported on the bottom head surface of steam generators (SG) in Korea. The PWSCC resistance of Ni base alloys which have intergranular carbides is higher than those which have intragranular carbides. Conversely, in oxidized acidic solutions like sodium sulfate or sodium tetrathionate solutions, the Ni base alloys with a lot of carbides at the grain boundaries and shows less stress corrosion cracking (SCC) resistance. The role of grain boundary carbides in SCC behavior of Ni base alloys was evaluated and effect of intergranular carbides on the SCC susceptibility were reviewed from the literature.

Mechanical and Antibacterial Properties of Copper-added Austenitic Stainless Steel (304L) by MIM

  • Nishiyabu, Kazuaki;Masai, Yoshikaze;Ishida, Masashi;Tanaka, Shigeo
    • Journal of Powder Materials
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    • v.9 no.4
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    • pp.227-234
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    • 2002
  • For the austenitic stainless steel (304L) manufactured by metal injection molding(MIM), the effects of copper content and sintering temperature on the mechanical properties, antibacterial activities, corrosion resistance, and electric resistances were investigated. The specimens were prepared by injection molding of the premixed powders of water-atomized 304 L and Cu with poly-acetyl binders. The green compacts were prepared with various copper contents from 0 to 10 wt.% Cu, which were debound thermally at 873 K for 7.2 ks in $N_2$gas atmosphere and subsequently sintered at various temperatures from 1323 K to 1623 K for 7.2 ks in Ar gas atmosphere. The relative density and tensile strength of the sintered compacts showed the minimum values at 5 and 8 wt.% Cu, respectively. Both the relative density and the tensile strength of the specimen with 10 wt.% Cu sintered at 1373 K showed the highest values, higher than those of copper-free specimen. Antibacterial activities investigated by the plastic film contact printing method for bacilli and the quantitative analysis of copper ion dissolved in water increased as the increase of the copper content to stainless steels. It was also verified by the measurement of pitting potential that the copper addition in 304 L could improve the corrosion resistance. Furthermore the electric conductivity increased with the increase of copper content.

Estimation of residual stress in welding of dissimilar metals at nuclear power plants using cascaded support vector regression

  • Koo, Young Do;Yoo, Kwae Hwan;Na, Man Gyun
    • Nuclear Engineering and Technology
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    • v.49 no.4
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    • pp.817-824
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    • 2017
  • Residual stress is a critical element in determining the integrity of parts and the lifetime of welded structures. It is necessary to estimate the residual stress of a welding zone because residual stress is a major reason for the generation of primary water stress corrosion cracking in nuclear power plants. That is, it is necessary to estimate the distribution of the residual stress in welding of dissimilar metals under manifold welding conditions. In this study, a cascaded support vector regression (CSVR) model was presented to estimate the residual stress of a welding zone. The CSVR model was serially and consecutively structured in terms of SVR modules. Using numerical data obtained from finite element analysis by a subtractive clustering method, learning data that explained the characteristic behavior of the residual stress of a welding zone were selected to optimize the proposed model. The results suggest that the CSVR model yielded a better estimation performance when compared with a classic SVR model.