• Title/Summary/Keyword: Creep-Rupture

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PWSCC of Alloy 600 components in PWRs-Part 2 (원자력 발전소 Alloy 600 부품의 PWSCC-Part 2)

  • Hwang, Seong Sik
    • CORROSION AND PROTECTION
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    • v.12 no.1
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    • pp.12-23
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    • 2013
  • 원자력 발전소 주요 부품에 사용되는 Alloy 600의 PWSCC 개시와 전파기구를 살펴보고 그 억제 기술을 소개하였다. ○ 균열은 경화된 표면 산화층이 깨질 경우, 입계부식, 공식(pitting), 열처리 또는 물속에 노출되었을 때 일어나는 선택부식(selective corrosion), MnS등 게재물의 용출등에 의해 시작된다. ○ 균열의 전파는 '느린 성장'과 '빠른 성장'으로 구별해 볼 수 있는데 빠른 균열성장은 균열 선단에서의 응력확대 계수(KI)가 균열이 전파하는 임계값(KIscc)을 넘는 경우에 일어난다. ○ Slip Dissolution/Film Rupture Model, Enhanced surface mobility model, Hydrogen assisted creep rupture, Internal oxidation 등의 모델이 제시되어 있으며 Internal oxidation 모델이 여러 실험자료로 잘 뒷 받침되고 있다. ○ PWSCC 억제 방안으로는 부식환경과의 격리 및 보수용접이 대표적이며 부품의 교체를 통한 안전 확보의 방안도 있다. 수소량 조절을 통한 억제 방안도 제시되어 있다. ○ Alloy 600 PWSCC열화 관리 전략프로그램은 결함 발생 가능성이 높은 부위 선정, 우선 순위에 따른 계획적인 검사, 결함이 발견될 경우 완화조치를 취하거나 필요시 교체/보수를 실시하고 그 운영프로그램을 지속적으로 갱신관리하는 방안으로 유지되어야 한다.

The creep rupture properties on welded joints of Cr-W pipe steels for boiler in advanced thermal power plant (석탄화력발전소 보일러 배관용 Cr-W계 강 용접부의 크리프 파단특성)

  • 이연수;유석현;공병욱;이경운;김정태
    • Proceedings of the KWS Conference
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    • 2004.05a
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    • pp.149-151
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    • 2004
  • 고효율, 대용량의 친환경적이며 경제적인 발전소건설을 위해 초초임계압(USC: Ultra Super Critical) 석탄화력발전소의 건설이 세계적인 추세이다. 이러한 USC발전소는 효율향상을 위해 증기온도와 압력의 상승, 경제적 운용을 위해 부하변동운전 적용확대가 필수적이다. (중략)

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Taylor Series-Based Long-Term Creep-Life Prediction of Alloy 617 (Taylor 급수를 이용한 617 합금의 장시간 크리프 수명 예측)

  • Yin, Song-Nan;Kim, Woo-Gon;Park, Jae-Young;Kim, Soen-Jin;Kim, Yong-Wan
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.34 no.4
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    • pp.457-465
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    • 2010
  • In this study, a Taylor series (T-S) model based on the Arrhenius, McVetty, and Monkman-Grant equations was developed using a mathematical analysis. In order to reduce fitting errors, the McVetty equation was transformed by considering the first three terms of the Taylor series equation. The model parameters were accurately determined by a statistical technique of maximum likelihood estimation, and this model was applied to the creep data of alloy 617. The T-S model results showed better agreement with the experimental data than other models such as the Eno, exponential, and L-M models. In particular, the T-S model was converted into an isothermal Taylor series (IT-S) model that can predict the creep strength at a given temperature. It was identified that the estimations obtained using the converted ITS model was better than that obtained using the T-S model for predicting the long-term creep life of alloy 617.

Microstructure and Creep Fracture Characteristics of Dissimilar SMA Welds between Inconel 740H Ni-Based Superalloy and TP316H Austenitic Stainless Steel (Inconel 740H 니켈기 초내열합금과 TP316H 스테인리스강의 이종금속 SMA 용접부의 미세조직과 크리프 파단 특성)

  • Shin, Kyeong-Yong;Lee, Ji-Won;Han, Jung-Min;Lee, Kyong-Woon;Kong, Byeong-Ook;Hong, Hyun-Uk
    • Journal of Welding and Joining
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    • v.34 no.5
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    • pp.33-40
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    • 2016
  • The microstructures and the creep rupture properties of dissimilar welds between the Ni-based superalloy Inconel 740H and the non-stabilized austenitic stainless steel TP316H have been characterized. The welds were produced by shielded metal arc (SMA) welding process with the AWS A5.11 Class ENiCrFe-3 filler metal, commonly known as Inconel 182 superalloy. Postweld heat treatment at $760^{\circ}C$ for 4 hours was conducted to form ${\gamma}^{\prime}$ strengthener in Inconel 740H. The austenitic weld metal produced by Inconel 182 had a dendritic microstructure, and grew epitaxially from the both sides of Inconel 740H and TP316H base metals. Since both Inconel 740H and TP316H did not undergo any solid-state transformation during welding process, there were no heat-affected-zone (HAZ) sub-regions and the coarsoned grains near the weld interface were limited to a narrow region. The hardness of Inconel 182 weld metal was ~220 Hv. The gradual hardness decrease was detected at HAZ of TP316H, and the TP316H base metal displayed the lowest hardness value (~180 Hv) whilst the Inconel 740H showed the highest hardness value (~400 Hv). Fracture after creep occurred at the center of weld metal, regardless of creep condition. It was found that during creep the cracks initiated and propagated along interdendritic regions and grain boundaries at which Laves particles enriched in Nb, Si and Cr were present. The appropriate design of weld metal was discussed to suppress the creep-induced cracking of the present dissimilar weld.

Study on the Relationship Between Microstructure and Creep-Rupture Behavior of GTD 111 (Ni기 초내열합금 GTD 111의 크리프 파단에 미치는 미세조직의 영향)

  • Sin, Hyeon-Jong;Kim, In-Su;Lee, Jae-Hyeon;Heo, Seong-Gang;Jo, Chang-Yong
    • Korean Journal of Materials Research
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    • v.11 no.1
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    • pp.8-14
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    • 2001
  • Microstructural evolution and creep failure behavior of GTD 111 have been studied. Solidification and precipitation behaviors of the alloy during casting have been analyzed by microstructural observations. It has been found that MC carbides solidify just before the $\gamma$/$\gamma$' eutectic solidification. The ηphase was found to be formed by transformation of Ti-rich $\gamma$'phase. PFZ has formed in the vicinity of the transformed $\eta$ phase. A few MC particles, which have been identified as TaC, precipitated within the PFZ. Creep failure along grainboundary was dominant at and above $871^{\circ}C$. Creep failure above$ 871^{\circ}C$ was caused by the propagation of surface cracks and internal cracks. Creep crack has initiated at the microporosities embedded on the grainboundary. The $\eta$phase and PFZ have been found to be little or no effect on creep crack initiation.

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Calculation of Maximum Allowabel Temperature Difference for Life Design of Valve Casings for Steam Turbines of Fossil Power Plants (화력발전용 증기터빈 밸브 케이싱의 수명 설계를 위한 최대허용온도차 계산)

  • Ha, Joon-Wook;Kim, Tae-Woan;Lee, Boo-Youn
    • Journal of the Korean Society for Precision Engineering
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    • v.16 no.8
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    • pp.46-52
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    • 1999
  • Large valves for steam turbines of fossil power plants are exposed to a severe mechanical and thermal loading resulting from steam with high pressure and high temperature. Valve casings are designed to withstand such a loading. During the operation of a plant, temperatures at inner and outer surface of the casings are measured and steam flow is controlled so that the measured difference is lower than the maximum allowable value determined in the design stage. In this paper, a method is presented to calculate the maximum allowable temperature difference at the inner and outer surface of valve casings for steam turbines of fossil power plants. The finite element method is used to analyze distribution of temperature and stresses of a casing under the operating condition. Low cycle fatigue and creep rupture are taken into consideration to determine the maximum allowable temperature difference. The method can be usefully applied in the design stage of the large valves for the steam turbines, contributing to safe and reliable operation of the fossil power plants.

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STEAM GENERATOR TUBE INTEGRITY ANALYSIS OF A TOTAL LOSS OF ALL HEAT SINKS ACCIDENT FOR WOLSONG NPP UNIT 1

  • Lim, Heok-Soon;Song, Tae-Young;Chi, Moon-Goo;Kim, Seoung-Rae
    • Nuclear Engineering and Technology
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    • v.46 no.1
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    • pp.39-46
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    • 2014
  • A total loss of all heat sinks is considered a severe accident with a low probability of occurrence. Following a total loss of all heat sinks, the degasser/condenser relief valves (DCRV) become the sole means available for the depressurization of the primary heat transport system. If a nuclear power plant has a total loss of heat sinks accident, high-temperature steam and differential pressure between the primary heat transport system (PHTS) and the steam generator (SG) secondary side can cause a SG tube creep rupture. To protect the PHTS during a total loss of all heat sinks accident, a sufficient depressurization capability of the degasser/condenser relief valve and the SG tube integrity is very important. Therefore, an accurate estimation of the discharge through these valves is necessary to assess the impact of the PHTS overprotection and the SG tube integrity of the primary circuit. This paper describes the analysis of DCRV discharge capacity and the SG tube integrity under a total loss of all heat sink using the CATHENA code. It was found that the DCRV's discharge capacity is enough to protect the overpressure in the PHTS, and the SG tube integrity is maintained in a total loss of all heat accident.

The Study for Fracture in the First Stage Blade of Aircraft Engine (항공기엔진용 1단계 터빈블레이드에 대한 파손 연구)

  • Yoon, Youngwoung;Park, Hyoungkyu;Kim, Jeong
    • Journal of the Korean Society for Aeronautical & Space Sciences
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    • v.46 no.10
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    • pp.806-813
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    • 2018
  • The fracture of a turbine blade of aerospace engine is presented. Although there are a lot of causes and failure modes in blades, the main failure modes are two ways that fracture and fatigue. Degradation of blade material affects most failure modes. Total propagation of failure in this study specifies failure of fracture type. Some section appears fatigue mode. Especially since this study describes analysis of failure for blade in high temperature, it can be a case in point. Analysed blade is Ni super alloy. Investigations of blade are visual inspection, material, microstructure, high temperature stress rupture creep test, analysis and fracture surface, etc. The root cause for fracture was stress rupture due to abnormal thermal environment. Thermal property of Ni super alloy is excellent but if each chemical composition of alloys are different due to change mechanical properties, selection of material is very important.

Low Cycle Fatigue Life Prediction of Reusable Experimental Liquid Rocket Engine (재사용이 가능한 실험용 액체로켓엔진의 저주기 피로수명예측)

  • 한풍규;송준영
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2002.04a
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    • pp.8-9
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    • 2002
  • 액체로켓엔진의 연소기는 고온고압의 연소가스에 의해 벽면온도가 매우 높은 수준에 도달하기 때문에, 연소기가 열적으로 안정적으로 작동할 수 있는 메카니즘이 필요하게 되며, 따라서 이러한 방식의 하나로서 추진제를 이용한 재생냉각방식이 널리 사용되고 있다. 일반적으로 재생냉각형 연소기의 내벽은 열전도도가 우수한 구리 또는 구리합금 계열이 많이 사용되고 있다. 이러한 내벽 재질의 내구성은 주로 creep rupture, low cycle thermal fatigue, thermal-mechanical ratcheting에 의해 결정되는데, 사각형태의 냉각채널의 연소기에서는 thermal-mechanical ratcheting 특성이 수명 결정 주요 인자이다. Thermal-mechanical ratcheting은 그림 1과 같이 연소가스 영역과 냉각제 영역을 분리하는 벽면에서 국부적인 부풀음이 일어나면서 벽면두께가 감소하는 소성변형 형태로 나타나는데, 이러한 것을 Dog- house 형상이라 한다.

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Creep Rupture Due to Molybdenum Rich $M_6C$ Carbide in 1.0Cr-1.0Mo-0.25V Steel Weldment (1.0Cr-1.0Mo-0.25V강 용접부의 $M_6C$ 탄화물에 의한 크립 파단)

  • O, Yeong-Geun;Kim, Byeong-Cheol;Gang, Gye-Myeong;Min, Tae-Guk
    • Korean Journal of Materials Research
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    • v.6 no.12
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    • pp.1257-1262
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    • 1996
  • 1.0Cr-1.0Mo-0.25V강 용접부의 크립 파단 시험시 파단 발생 원인에 관한 연구가 시행되었다. 파괴는 Intercritical Heat Affected Zone에서 발생하였으며 파단면에서 구상의조대한 M6C탄화물이 발견되었다. 모재는 molybdenum 주성분의 M2C, vanadium 주성분의 M4C3 및 chromium 주성분의 M23C6와 M7C3 탄화물이 존재하였다. 모의 실험 결과 준안정 상태인 M2C 탄화물은 85$0^{\circ}C$, 10oh에서 안정한 M6C탄화물로 변태하였다. M6C 탄화물은 주변의 molybdenum 농도를 떨어뜨려 강도의 저하를 가져오며 크립 기공의 발생 원인을 제공하였다.

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