• Title/Summary/Keyword: water corrosion

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Preparation and Properties of ρ-alumina Bonded Alumina Vibrated Castable Refractory (진동성형용 ρ-알루미나결합 알루미나 캐스터블 내화재료의 제조와 특성)

  • 천승호;전병세
    • Journal of the Korean Ceramic Society
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    • v.40 no.8
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    • pp.791-797
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    • 2003
  • The special binding mechanism developed provides higher density, lower porosity and higher strengths compared with conventional castables. $\rho$-alumina was employed as a binder materials and nano-sized clay colloidal was added to enhance the drying strength preparing for the alumina vibrated castable. Lower water requirement for casting results in a denser product. The mechanical properties with dimensional stability and corrosion resistance behaviors have been improved by controlling the matrix compositions of the castable. The modulus of rupture and compressive strength after heat treatment at 150$0^{\circ}C$ are 92.34 kgf/$\textrm{cm}^2$ and 370 kgf/$\textrm{cm}^2$ respectively. The activation energy of mullite formation is 11.47 kcal/mol.

Case Study of Intermittent Poor Acceleration Fault Diagnosis by Brake Switch Fault (브레이크 스위치 결함에 의한 간헐적인 가속불량 현상의 고장진단 사례연구)

  • Kim, Sung Mo;Jo, Haeng Deug
    • Journal of the Korean Society of Manufacturing Technology Engineers
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    • v.24 no.2
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    • pp.203-210
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    • 2015
  • This paper investigates the failure of a car with a 2.5-liter CRDi engine of the Hyundai Company. The failure is caused by intermittent poor acceleration while driving. To analyze the cause, we investigated the air intake volume, the fuel injection, and the air-fuel ratio, which were determined to be normal. The brake switch signal error was discovered while analyzing the function that limits the output of the engine. While investigating the cause, we discovered the corrosion of the pins on the connector of the brake switch. We determined that it was generated by soapy water flowing in the solar film. Therefore, the cause of the failure was the brake switch signal errors. Additionally, we determined that ECM was the normal fail-safe mode that implemented the override device for safety during normal acceleration. Based on these results, further solar film experiments must be conducted to fully elucidate the causes.

A Review of the Progress with Statistical Models of Passive Component Reliability

  • Lydell, Bengt O.Y.
    • Nuclear Engineering and Technology
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    • v.49 no.2
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    • pp.349-359
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    • 2017
  • During the past 25 years, in the context of probabilistic safety assessment, efforts have been directed towards establishment of comprehensive pipe failure event databases as a foundation for exploratory research to better understand how to effectively organize a piping reliability analysis task. The focused pipe failure database development efforts have progressed well with the development of piping reliability analysis frameworks that utilize the full body of service experience data, fracture mechanics analysis insights, expert elicitation results that are rolled into an integrated and risk-informed approach to the estimation of piping reliability parameters with full recognition of the embedded uncertainties. The discussion in this paper builds on a major collection of operating experience data (more than 11,000 pipe failure records) and the associated lessons learned from data analysis and data applications spanning three decades. The piping reliability analysis lessons learned have been obtained from the derivation of pipe leak and rupture frequencies for corrosion resistant piping in a raw water environment, loss-of-coolant-accident frequencies given degradation mitigation, high-energy pipe break analysis, moderate-energy pipe break analysis, and numerous plant-specific applications of a statistical piping reliability model framework. Conclusions are presented regarding the feasibility of determining and incorporating aging effects into probabilistic safety assessment models.

Improvement of Structural Performance for the Precast Box Culvert (지하 프리캐스트 박스 암거의 구조적 성능 개선에 관한 연구)

  • 조병완;태기호;이계삼
    • Proceedings of the Korea Concrete Institute Conference
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    • 2000.04a
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    • pp.393-398
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    • 2000
  • To use concrete box culverts effectively, precast goods are manufactured at a factory, then linked and anchored with prestressing tendon at a field. However, the corrosion of rebar and prestressing tendon in the box culverts utilizing portland cement concrete is issued when the cracks occur at a underground water level. It has been reported that reported that expansive concrete, compared with portland cement concrete, has many structural advantages such as increasing capacity of watertight, controling initial crack and improving durability due to its property of expansion. During flexure test with RC beam made from expansive concrete, in the case of a constant section of concrete element, the lower steel ratio is, and in the case of a constant steel ratio, the more incremental the section of concrete element, the more incremental the amount of chemical prestress by expansive concrete is. At the segment of the box culverts using expansive concrete, the numbers of crack and its gap is reduced, and ultimate load and initial crack load is much larger than the segment at which expansive concrete is nor used. Also lay-out of tendon with a curvature generate upward force so that deflection is reduced. Through the whole procedure, it could be confirmed that performance precast box culvert by means of using expansive concrete is improved.

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Structural Analysis for the Determination of Design Variables of Spent Nuclear Fuel Disposal Canister

  • Youngjoo Kwon;Shinuk Kang;Park, Jongwon;Chulhyung Kang
    • Journal of Mechanical Science and Technology
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    • v.15 no.3
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    • pp.327-338
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    • 2001
  • This paper presents the results of a structural analysis to determine design variables such as the inner basket array type, and thicknesses of the outer shell, and lid and bottom of a spent nuclear fuel disposal canister. The canister construction type introduced here is a solid structure with a cast iron insert and a corrosion resistant overpack, which is designed for the spent nuclear fuel disposal in a deep repository in the crystalline bedrock, entailing an evenly distributed load of hydrostatic pressure from the groundwater and high swelling pressure from the bentonite buffer. Hence, the canister must be designed to withstand these high pressure loads. Many design variables may affect the structural strength of the canister. In this study, among those variables, the array type of inner baskets and thicknesses of outer shell and lid and bottom are attempted to be determined through a linear structural analysis. Canister types studied hear are one for the pressurized water reactor (PWR) fuel and another for the Canadian deuterium and uranium reactor (CANDU) fuel.

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Residual Stress Analysis of the Overlay Weld on the Dissimilar Metal Butt Weld (이종재이종재료 Butt 용접에 대한 Overlay 용접의 잔류응력해석)

  • Kim, Kang-Soo;Lee, Ho-Jin;Lee, Bong-Sang;Jung, In-Chul;Byeon, Jin-Gwi;Park, Kwang-Soo
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.534-537
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    • 2008
  • In recent years, the dissimilar metal, Alloy 82/182 welds used to connect stainless steel piping and low alloy steel or carbon steel components in nuclear reactor piping system have experienced cracking due to primary water stress corrosion(PWSCC). It is well known that one reason of the cracking is the residual stress by the weld. But, it is difficult to estimate exactly weld residual stress due to many parameters of welding. In this paper, the analysis of 3 FEM models made by ABAQUS Code is performed to estimate exactly the weld residual stress on the dissimilar metal weld. 3 FEM models are Butt model, Repair model and Overlay model and are the plane.strain 2D model. The thermal analysis and the stress analysis are performed on each model and the residual stresses on each model were calculated and compared respectively. Also, the specimen of Butt model was made and the residual stresses were measured by X-Ray method and Hole Drilling Technique. These results were compared with the FEM result of Butt model.

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Results and analyses for simulational round robin on welding residual stress prediction in nuclear power plant nozzle (원전 노즐 용접부 잔류응력 예측에 대한 유한요소 해석 Round Robin 결과 및 분석)

  • Song, Tae-Kwang;Bae, Hong-Yeol;Kim, Yun-Jae;Lee, Kyoung-Soo;Park, Chi-Yong;Yang, Jun-Seog;Huh, Nam-Su;Kim, Jong-Wook;Park, June-Soo;Song, Min-Sup;Lee, Seung-Gun;Kim, Jong-Sung;Yu, Seung-Cheon;Chang, Yoon-Suk
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.79-82
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    • 2008
  • In this paper, results of simulational round robin test on residual stress prediction was provided. Welding residual stress is one of the reasons for primary water stress corrosion cracking in PWR. Therefore, quantifying the welding variables and defining the recommendation for prediction welding residual stress is important. Through the round robin test, it is known that compressive axial and hoop residual stress occurs in dissimilar metal weld and pre-existing residual stress distribution in dissimilar metal weld was affected by similar metal weld due to short length of safe end.

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Effect of Corrosion inhibitor, Benzotriazole (BTA), on Particle Adhesion in Cu CMP (Cu CMP중 BTA에 의한 Particle의 흡착에 관한 연구)

  • Song, Jae-Hoon;Hong, Yi-Koan;Kim, Tae-Gon;Park, Jin-Goo
    • Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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    • 2005.11a
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    • pp.366-367
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    • 2005
  • The effect of benzotriazole (BTA) on the adhesion force of silica and pad particle on Cu/TEOS wafer surfaces was investigated with and without the addition of BTA. Cu-BTA had the isoelectric point (IEP) at around pH 4$\sim$8. Pad particles were more positive zeta potentials than silica. The adhesion force initially decreased of silica and pad particle on Cu surfaces when BTA was added. However, the more BTA was added, the more adhesion force gradually increased with the increase of BTA concentrations. Then the adhesion force of pad particle was higher than silica. And TEOS didn't resulted increasing adhesion force like Cu when BTA was added in DI water.

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Preliminary Round Robin Test(RRT) for Program for the Inspection of Nickel Alloy Components(PINC) - Reactor Vessel Head Penetration (RVHP) -

  • Kim, Kyung-Cho;Kang, Sung-Sik;Shin, Ho-Sang;Song, Myung-Ho;Chung, Hae-Dong;Kim, Yong-Sik
    • Journal of the Korean Society for Nondestructive Testing
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    • v.29 no.3
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    • pp.256-263
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    • 2009
  • After several PWSCCs were found in Bugey(France), Ringhals(Sweden), Tihange(Belgium), Oconee, Arkansas, Crystal Fever, Davis-Basse, VC Summer(U.S.A.), Thuruga(Japan), USNRC and PNNL started the research on PWSCC, that is, the PINC project. USNRC required KINS to participate in the PINC project in May 2005. KINS organized the Korean consortium at March 2006 and Pre-RRT for RVHP were performed for the preparation of PINC RRT. Through these preliminary RRT, Korea NDE teams can learn and develop the detection and sizing technique for RVHP dissimilar metal weld. These techniques are now being prepared in Korea and need to be utilized for the In-service inspection of the RVHP and BMI of Korea Nuclear Power Plants. PINC RRT mock-ups will be helpful to training.

Design of Nickel Alloys Using the Theoretical Values Calculated from the Electronic State Energies (에너지 전자상태 계산으로 도출된 이론값을 이용한 니켈 합금 설계)

  • Baek, Min-Sook;Kang, Pub-Sung;Baek, Kyeong-Cheol;Kim, Byung-Il;Yoon, Dong-Joo
    • Korean Journal of Materials Research
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    • v.25 no.11
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    • pp.642-646
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    • 2015
  • Super alloys, which can be divided into three categories, i.e. Ni-base, Co-base, and Fe-base alloys, are widely used for high temperature applications. Since superalloys contain many alloying elements and precipitates, their chemistry and processing parameters need to be carefully designed. In this study, we designed a new Ni alloy to prevent corrosion due to water vapor and gases at high temperatures. The new alloy was designed using the theoretical value of the resulting energy electronic state calculation($DV-X{\alpha}$ method). The components that were finally used were Cr, Mo, and Ti, with Ni as a base. For these alloys, elements were selected in order to compare their values with that of the average theoretical basis for an Inconel 625 alloy. Finally, two kinds of Ni alloy were designed: Ni-28Cr-4Mo-2Ti and Ni-20Cr-10Mo-1Ti.