• Title/Summary/Keyword: stress corrosion

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Corrsion behavior of Al-Mg-Zn Alloys by homogenization heat treatment (균질화 처리에 따른 Al-Mg-Zn 합금의 내식성 거동)

  • Jo, Yu-Sin;Choe, In-Gyu;Kim, Sang-Ho
    • Proceedings of the Korean Institute of Surface Engineering Conference
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    • 2017.05a
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    • pp.139-139
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    • 2017
  • 최근 환경오염 문제로 인한 연비 규제 강화 속도가 빨라지고 있으며 이에 따른 연비 향상 기술이 크게 대두 되고 있다. 연비 향상 기술 중 경량화 방안소재로 알루미늄(Al), 마그네슘(Mg) 등의 비철금속을 주로 사용하고 있으며, 이중 알루미늄은 다른 경량화 금속소재보다 우수한 경쟁력을 가지고 있다. 하지만 경제적인 측면에서 철 대비 비용적인 어려움을 가지고 있고 용접성이 떨어지기 때문에, 자동차 부품의 일부만 알루미늄 소재를 선택하여 사용하고 있는 실정이며 알루미늄의 높은 이온화 경향으로 인해 기존 자동차 철강 소재와 접촉 시 쉽게 부식되는 단점을 가지고 있다. 이러한 문제점을 해결하기 위해서는 알루미늄의 금속원소를 첨가하는 연구가 지속적으로 개발 되고 있다. 알루미늄 합금에서 마그네슘의 첨가는 좋은 용접성과 내식성, 강도를 향상시킨다. 하지만 3%이상의 마그네슘 첨가는 입계에 ${\beta}(Al_xMg_y)$석출상이 석출되게 되며, 입계에 연속적으로 형성된 ${\beta}(Al_xMg_y)$석출상은 응력 부식 균열 (Stress corrsion cracking)과 입계 부식(Intergranular corrosion)을 야기하는 결과를 가져온다고 알려져 있다. 이 문제를 해결하기 위해 Al 5000계열 합금의 Zn의 첨가를 통해 ${\tau}(Al_xMg_yZn_z)$을 입계에 석출시켜서 입계에 ${\beta}(Al_xMg_y)$상의 석출을 방지함으로써 내식성을 향상시키거나 Al 5000계열 합금의 열처리를 통해 ${\beta}(Al_xMg_y)$석출상을 고용시킴으로써 응력부식균열의 발생을 억제하는 연구도 있다. 하지만 열처리 후 Polarization test를 이용한 내식성 연구는 잘 안 알려져 있다. 따라서 이번 연구에서는 Al5000계열의 주조한 합금을 DSC분석을 통하여 ${\beta}(Al_xMg_y)$석출상의 고용 온도가 약 $470^{\circ}C$라는 것을 확인한 후, 실온에서 $100^{\circ}C/hr$으로 가열하고 조건에 따라 $450^{\circ}C$에서 3시간, 6시간, 12시간, 24시간, 30시간 항온 유지시킨 후 공냉을 진행하였다. 열처리를 마친 시편은 에폭시를 이용하여 마운팅 하였으며, 시편표면을 2000#까지 연마 후 증류수로 세척한 다음 질소를 이용하여 건조 후 분극 시험을 진행하였다. 3.5wt% NaCl 용액에서 분극 곡선을 통해 부식거동을 확인한 결과 24시간까지 시간이 증가 할수록 내식성이 우수해지는 것을 확인하였으며, 추가적으로 조직사진, SEM & EDS 분석과 XRD, TEM 분석을 통해 내식성은 입계에 존재하는 Mg의 조성이 감소하게 되면 내식성이 향상되는 것을 관찰하였다.

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The Integrity Verification of Tube-end Sleeve by ECT (와전류탐상검사에 의한 튜브엔드 슬리브 건전성 검증)

  • Kim, Su Jin;Kwon, Kyung Joo;Suk, Dong Hwa;Park, Ki Tae
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.1
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    • pp.20-24
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    • 2015
  • Steam generator(S/G) tubes in pressurized water reactor (PWR's) are subject to several types of degradation. This degradation includes denting, pitting, intergranular attack(IGA), intergranular stress corrosion cracking(IGSCC), fatigue, fretting and wear. Degradation can be derived from either the primary side(inside) or the secondary side(outside) of the tube. Recent issue for tube degradation in domestic steam generator is the tube end cracking on seal weld region. The seal weld region at the tube end and tube itself is regarded as a pressure boundary between the primary side and the secondary side. One of the Westinghouse Model-F S/G has experienced tube end cracking and its number of plugging approximately becomes to the operating limit up to 5% due to tube end cracking which was reported as SAI/MAI(single/multiple axial indication) or SCI/MCI(Single/multiple circumferential indication) from the results of eddy current testing. Eddy current mock-up test was carried out to determine the origin of cracking whether it is from weld zone area or parent tube. This result was helpful to analyze crack location on ECT data. Correct action on this problem was the installation of tube-end sleeve. Last year, after removing 340 installed plugs from tubes, selected 269 tubes took tube-end sleeve installation. Tube-end sleeve brought pressure boundary from parent tube to installed sleeve tube. Tube-end sleeve has the benefit of reducing outage period and increasing more revenue than replacing S/G. This paper is provided to assist interest parties in effectively understanding this issue.

AN EVALUATION OF DYNAMIC FATIGUE CHARACTERISTICS OF DENTAL CERAMICS FOR ALL-CERAMIC CROWN (All-ceramic Crown 용 도재의 동적 피로특성 평가)

  • Yu, Hyoung-Woo;Bae, Tae-Sung;Song, Kwang-Yeob;Park, Charn-Woon
    • The Journal of Korean Academy of Prosthodontics
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    • v.35 no.4
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    • pp.781-792
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    • 1997
  • This study was peformed to evaluate the dynamic fatigue characteristics of the dental ceramics for all-ceramic crown. A feldspathic porcelain of VMK68. glass ceramic of IPS-Empress, and glass infiltrated alumina ceramic of In-Ceram were used. Disc specimens were prepared to the final dimensions of 12 mm in diameter and 1 mm in thickness. The biaxial flexure test was conducted using a ball-on-three-ball method. 240 specimens were tested in $37^{\circ}C$ water by testing 20 samples at each of four loading rates:0.05, 0.2, 1, and 5mm/min. 60 specimens were tested in a moisture-free environment by testing 20 samples at 5mm/min. The inert strength of VMK68 was 80.25MPa, and the fatigue parameters were n=29.1, ${\sigma}_{fo}=52.90MPa$. The inert strength of IPS-Empress was 104.76MPa, and the fatigue parameters were n=32.46, ${\sigma}_{fo}=67.52MPa$. The inert strength of In-Ceram was 429.33MPa, and the fatigue parameters were n=31.46, ${\sigma}_{fo}=258.36MPa$. 10-year failure stresses of VMK68, IPS-Empress, and In-Ceram were 20.3MPa, 24.8MPa, and 93.6MPa, respectively. Failure strength and fatigue life showed the highest value in In-Ceram, and then, IPS-Empress and VMK68.

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Development the Technique for Fabrication of the Thermal Fatigue Crack to Enhance the Reliability of Structural Component in NPPs (원자력 구조재 신뢰성 향상을 위한 열피로 균열 시험편 제작 기법 개발)

  • Kim, Yong;Kim, Jae-Sung;Lee, Bo-Young
    • Journal of Welding and Joining
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    • v.26 no.2
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    • pp.43-49
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    • 2008
  • Fatigue cracks due to thermal stratification or corrosion in pipelines of nuclear power plants can cause serious problems on reactor cooling system. Therefore, the development of an integrated technology including fabrication of standard specimens and their practical usage is needed to enhance the reliability of nondestructive testing. The test material was austenitic STS 304, which is used as pipelines in the Reactor Coolant System of a nuclear power plants. The best condition for fabrication of thermal fatigue cracks at the notch plate was selected using the thermal stress analysis of ANSYS. The specimen was installed from the tensile tester and underwent continuos tension loads of 51,000N. Then, after the specimen was heated to $450^{\circ}C$ for 1 minute using HF induction heater, it was cooled to $20^{\circ}C$ in 1 minute using a mixture of dry ice and water. The initial crack was generated at 17,000 cycles, 560 hours later (1cycle/2min.) and the depth of the thermal fatigue crack reached about 40% of the thickness of the specimen at 22,000 cycles. As a results of optical microscope and SEM analysis, it is confirmed that fabricated thermal fatigue cracks have the same characteristics as real fatigue cracks in nuclear power plants. The crack shape and size were identified.

Preliminary PINC(Program for the Inspection of Nickel Alloy Components) RRT(Round Robin Test) - Pressurizer Dissimilar Metal Weld -

  • Kim, Kyung-Cho;Kang, Sung-Sik;Shin, Ho-Sang;Chung, Ku-Kab;Song, Myung-Ho;Chung, Hae-Dong
    • Journal of the Korean Society for Nondestructive Testing
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    • v.29 no.3
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    • pp.248-255
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    • 2009
  • After several damages by PWSCC were found in the world, USNRC and PNNL(Pacific Northwest National Laboratory) started the research on PWSCC under the project name of PINC. The aim of the project was 1) to fabricate representative NDE mock-ups with flaws to simulate PWSCCs, 2) to identify and quantitatively assess NDE methods for accurately detecting, sizing and characterizing PWSCCs, 3) to document the range of locations and morphologies of PWSCCs and 4) to incorporate results with other results of ongoing PWSCC research programs, as appropriate. Korea nuclear industries have also been participating in the project. Thermally and mechanically cracked-four mockups were prepared and phased array and manual ultrasonic testing(UT) techniques were applied. The results and lessons learned from the preliminary RRT are summarized as follows: 1) Korea RRT teams performed the RRT successfully. 2) Crack detection probability of the participating organizations was an average 87%, 80% and 80% respectively. 3) RMS error of the crack sizing showed comparatively good results. 4) The lessons learned may be helpful to perform the PINC RRT and PSI /ISI in Korea in the future.

Development of Automated Nondestructive Inspection System for BMI Nozzles in Nuclear Vessel (원자로 BMI 노즐 검사를 위한 자동화 비파괴검사 시스템 개발)

  • Park, Joon Soo;Lee, Won Kun;Han, Won Jin;Lee, Sun Ho;Seong, Un Hak
    • Journal of the Korean Society for Nondestructive Testing
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    • v.33 no.1
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    • pp.26-33
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    • 2013
  • BMI nozzles in bottom head of the nuclear vessel are one of major components in nuclear power plants. The BMI nozzles have high possibility to generate PWSCC(primary water stress corrosion crack) according to recent foreign case although operation temperature is lower then the upper head of the nuclear vessel. Thus, nondestructive inspection of the BMI nozzles is required. But, inspection of BMI nozzles is not easy since the BMI nozzles placed in high radiated area and inside the nozzles filled with boric acid. Thus, in this study, a TOFD transducer for inspection of BMI and automated scanner system with water were developed. Also, validation of performance of the developed transducer and system are performed using specimens with artificial defects.

A Study of Weldability for Pure Titanium by Nd:YAG Laser(IV) - Lap Welding and Application for Heat Exchanger - (순티타늄판의 Nd:YAG 레이저 용접성에 관한 연구(IV) - 겹치기 용접 및 실물 열교환기로의 적용 -)

  • Kim, Jong-Do;Kwak, Myung-Sub;Lee, Chang-Je;Kil, Byung-Lea
    • Journal of Welding and Joining
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    • v.28 no.1
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    • pp.66-71
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    • 2010
  • With large specific strength and outstanding corrosion resistance and erosion resistance in sea water, titanium and titanium alloy are widely used in heat exchanger production. In particular, pure titanium demonstrates outstanding molding performance and may be considered optimal for production of heat exchanger. Since titanium is very vulnerable to oxidation and embrittlement during welding, processes with less heat input are widely used, and laser welding is widely applied by considering production performance and shield etc in atmosphere. So far, 1st report and 2nd report compared and analyzed embrittlement degrees by bead colors of weldment through oxygen and nitrogen quantitative analysis and hardness measurement, and evaluated welding performance and mechanical properties of butt welding. This study evaluated field applicability of lap welding to heat exchange plate of LPG re-liquefaction device for ships through tensile stress test, hardness test and internal pressure test etc after deducing optimal weding condition and applying to actual heat exchange plate. In bead overlap area, the experiment produced sound welds with no porosity or defect by increasing and decreasing laser power, and tensile-shear test results indicated virtually the same tension and yield strength as base metal. As a result of measuring hardness at lateral cross section and bead overlap zone of actual heat exchanger welds, hardness difference within 20Hv was produced at base metal, HAZ and weldment, and as a result of pneumatic and hydraulic pressure test, no leakage occurred.

Development of Automated Ultrasonic Testing System for Partial Joint-Weld of Heat Exchanger's Header to Tube in Power Plant (발전소 열교환기 헤더와 튜브의 부분 용입형 용접부 초음파 자동검사시스템 개발)

  • Lee, Jin-Hyuk;Lim, Seong-Jin;Park, Ik-Keun;Kim, Dae-Hyun
    • Journal of the Korean Society for Nondestructive Testing
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    • v.30 no.4
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    • pp.367-372
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    • 2010
  • A power plant's heat exchangers work under poor conditions, such as high temperature, high pressure, corrosion, mechanical stress and vibration. Especially, partial joint-weld of heat exchanger's header to stub-tube is the place where incomplete penetration flaws can easily occur. But, it is hard to evaluate the safety of the structure by conventional nondestructive testing techniques. So it is necessary to test integrity of the weld inside and to develop testing technique and equipment that can detect the flaws at the weld point in order to enhance reliability of the test result. In this study, we developed a suitable automated ultrasonic testing system that can inspect the partial joint-weld of header to stub-tube of power plant. Finally, we showed the efficiency of the automated ultrasonic-testing-system from the application.

A Study on the high Temperature Properties of the Graded Thermal Barrier Coatings by APS and PAS (APS법으로 제조된 열장벽 피막과 PAS법으로 제조된 열장벽 성형체의 고온 물성에 관한 연구)

  • 강현욱;권현옥;한주철;송요승;홍상희;허성강;김선화
    • Journal of the Korean institute of surface engineering
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    • v.32 no.2
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    • pp.144-156
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    • 1999
  • Thermal Barrier Coating with Functional Gradient Materials (FGM-TBC) can play an important role to protect the parts from harmful environments in high temperatures such as oxidation, corrosion, and wear and to improve the efficiency of aircraft engine by lowering the surface temperature on turbine blade. FGM-TBC can increase the life spans of product and improve the operating properties. Therfore, in this study the evaluations of mechanical and thermal properties of FGM-TBC such as fatigue, oxidation and wear-resistance at high temperatures have been conducted. The samples of both the TBC with 2, 3, 5 layers (YSZ/NiCrAlY) to be produced by Air Plasma Spray method (APS) and the bulk TBC with 6 layers to be produced by Plasma Assisted Sintering method (PAS) were used. Furthermore, residual stress, bond strength, and thermal conductivity were evaluated. The average thickness of the APS was 500$\mu\textrm{m}$ to 600$\mu\textrm{m}$ and the average thickness of the PAS was 3mm. The hardness number of the top layer of APS was 750 Hv to 810Hv and that of PAS was 950 Hv to 1440Hv. The $ZrO_2$ coating layer of APS was composed of tetragonal structure after spraying as the result of XRD analysis. As shown in the results of the high temperature wear test, the 3 layer coating of APS had the best wear resistance at $800^{\circ}C$ and the 5 layer coating of APS had the best wear resistance at $600^{\circ}C$. But, these coatings had the tendency of the low-temperature softening at $300^{\circ}C$. The main mechanism of wear was the adhesive wear and the friction coefficient of coatings was increased as increasing the test temperatures. A s results of thermal conductivity test, the ${\Delta}T$ of the APS coating was increased as number of layer and the range of thermal conductivity of the PAS was $800^{\circ}C$ to $1000^{\circ}C$.

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