• Title/Summary/Keyword: PWSCC Initiation Model

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PWSCC Growth Assessment Model Considering Stress Triaxiality Factor for Primary Alloy 600 Components

  • Kim, Jong-Sung;Kim, Ji-Soo;Jeon, Jun-Young;Kim, Yun-Jae
    • Nuclear Engineering and Technology
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    • v.48 no.4
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    • pp.1036-1046
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    • 2016
  • We propose a primary water stress corrosion cracking (PWSCC) initiation model of Alloy 600 that considers the stress triaxiality factor to apply to finite element analysis. We investigated the correlation between stress triaxiality effects and PWSCC growth behavior in cold-worked Alloy 600 stream generator tubes, and identified an additional stress triaxiality factor that can be added to Garud's PWSCC initiation model. By applying the proposed PWSCC initiation model considering the stress triaxiality factor, PWSCC growth simulations based on the macroscopic phenomenological damage mechanics approach were carried out on the PWSCC growth tests of various cold-worked Alloy 600 steam generator tubes and compact tension specimens. As a result, PWSCC growth behavior results from the finite element prediction are in good agreement with the experimental results.

Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects

  • Park, Jae Phil;Yoo, Seung Chang;Kim, Ji Hyun;Bahn, Chi Bum
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.1909-1923
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    • 2021
  • We experimentally investigated the effects of thermal aging and cold work on the microstructure, mechanical properties, and primary water stress corrosion cracking (PWSCC) initiation time for Alloy 182 welds. The effects of thermal aging and cold work on the PWSCC initiation time of Alloy 182 were modeled based on the plastic energy concept and the PWSCC initiation data of this study and previous reports by considering censored data. Based on the results, it is estimated that the PWSCC resistance of the Alloy 182 weld firstly increases and then decreases with thermal aging time when the applied stress is kept constant.

Effects of Hydrogen on the PWSCC Initiation Behaviours of Alloy 182 Weld in PWR Environments

  • Kim, H.-S.;Hong, J.-D.;Lee, J.;Gokul, O.S.;Jang, C.
    • Corrosion Science and Technology
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    • v.14 no.3
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    • pp.113-119
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    • 2015
  • Alloy 82/182 weld metals had been extensively used in joining the components of the PWR primary system. Unfortunately, there have been a number of incidents of cracking caused by PWSCC in Alloy 82/182 welds during the operation of PWR worldwide. To mitigate PWSCC, optimization of water-chemistry conditions, especially dissolved hydrogen (DH) and Zn contents, is considered as the most promising and effective remedial method. In this study, the PWSCC behaviours of Alloy 182 weld were investigated in simulated PWR environments with various DH content. Both in-situ and ex-situ oxide characterizations as well as PWSCC initiation tests were performed. The results showed that PWSCC crack initiation time was shortest in PWR water (DH: 30cc/kg). Also, high stress reduced crack initiation time. Oxide layer showed multi-layered structures consisted of the outer needle-like Ni-rich oxide layer, Fe-rich crystalline oxide, and inner Cr-rich inner oxide layers, which was not altered by the level of applied stress. To analyse the multi-layer structure of oxides, EIS measurement were fitted into an equivalent circuit model. Further analyses including TEM and EDS are underway to verify appropriateness of the equivalent circuit model.

PFM APPLICATION FOR THE PWSCC INTEGRITY OF Ni-BASE ALLOY WELDS-DEVELOPMENT AND APPLICATION OF PINEP-PWSCC

  • Hong, Jong-Dae;Jang, Changheui;Kim, Tae Soon
    • Nuclear Engineering and Technology
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    • v.44 no.8
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    • pp.961-970
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    • 2012
  • Often, probabilistic fracture mechanics (PFM) approaches have been adopted to quantify the failure probabilities of Ni-base alloy components, especially due to primary water stress corrosion cracking (PWSCC), in a primary piping system of pressurized water reactors. In this paper, the key features of an advanced PFM code, PINEP-PWSCC (Probabilistic INtegrity Evaluation for nuclear Piping-PWSCC) for such purpose, are described. In developing the code, we adopted most recent research results and advanced models in calculation modules such as PWSCC crack initiation and growth models, a performance-based probability of detection (POD) model for Ni-base alloy welds, and so on. To verify the code, the failure probabilities for various Alloy 182 welds locations were evaluated and compared with field experience and other PFM codes. Finally, the effects of pre-existing crack, weld repair, and POD models on failure probability were evaluated to demonstrate the applicability of PINEP-PWSCC.

Investigation on Effect of Distance Between Two Collinear Circumferential Surface Cracks on Primary Water Stress Corrosion Crack Growth in Alloy 600TT Steam Generator Tubes (Alloy 600TT 증기발생기 전열관내 일렬 원주방향 표면 일차수응력 부식균열 성장에 미치는 균열 간격의 영향 고찰)

  • Heo, Eun-Ju;Kim, Jong-Sung;Jeon, Jun-Young;Kim, Yun-Jae
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.3
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    • pp.269-273
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    • 2015
  • The study investigated the effect of the distance between two collinear circumferential surface cracks on the primary stress corrosion crack (PWSCC) growth in alloy 600TT steam generator tubes using a finite element damage analysis based on the PWSCC initiation model and macroscopic phenomenological damage mechanics approach. The damage analysis method was verified by comparing the results to the previous study results. The verified method was applied to collinear circumferential surface PWSCCs. As a result, it was found that the collinear cracks showed earlier coalescence and penetration times than the a single crack, and the times increased with the distance. In addition, it is expected that penetration may occur before coalescence of two cracks if they are more than a specific distance apart.

Statistical analysis of parameter estimation of a probabilistic crack initiation model for Alloy 182 weld considering right-censored data and the covariate effect

  • Park, Jae Phil;Park, Chanseok;Oh, Young-Jin;Kim, Ji Hyun;Bahn, Chi Bum
    • Nuclear Engineering and Technology
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    • v.50 no.1
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    • pp.107-115
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    • 2018
  • To ensure the structural integrity of nuclear power plants, it is essential to predict the lifetime of Alloy 182 weld, which is used for welding in nuclear reactors. The lifetime of Alloy 182 weld is directly related to the crack initiation time. Owing to the large time scatter in most crack initiation tests, a probabilistic model, such as the Weibull distribution, has mainly been adopted for prediction. However, since statistically more advanced methods than current typical methods may be applied, we suggest a statistical procedure for parameter estimation of the crack initiation time of Alloy 182 weld, considering right-censored data and the covariate effect. Furthermore, we suggest a procedure for uncertainty evaluation of the estimators based on the bootstrap method. The suggested statistical procedure can be applied not only to Alloy 182 weld but also to any material degradation data set including right-censored data with covariate effect.