Evaluation of J-groove weld residual stress and crack growth rate of PWSCC in reactor pressure vessel closure head

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• 作者：Seung Hyuk Oh (1)
  Tae Young Ryu (1)
  Seung Hyun Park (1)
  Min Gu Won (1)
  Seok Jun Kang (1)
  Kyoung Soo Lee (2)
  Sung Ho Lee (2)
  Moon Ki Kim (1) (3)
  Jae Boong Choi (1) (3)
  
  1. School of Mechanical Engineering ; Sungkyunkwan University ; Suwon ; 440-746 ; Korea
  2. Central Research Institute ; Korea Hydro & Nuclear Power ; Daejeon ; 305-343 ; Korea
  3. SKKU Advanced Institute of Nanotechnology ; Sungkyunkwan University ; Suwon ; 440-746 ; Korea
  
• 关键词：Finite element analysis ; J ; groove weld ; Primary water stress corrosion crack ; Residual stress ; Crack growth rate
• 刊名：Journal of Mechanical Science and Technology
• 出版年：2015
• 出版时间：March 2015
• 年：2015
• 卷：29
• 期：3
• 页码：1225-1230
• 全文大小：3,222 KB
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  4. White, G. A., Nordmann, N. S., Hickling, J., Harrington, C. D. (2005) Development of crack growth rate disposition curves for Primary Water Stress Corrosion Cracking (PWSCC) of alloy 82, 182, and 132 weldments. 12 th International Conference on Environmental Degradation of Materials in Nuclear Power System, Salt Lake City, USA. pp. 511-531
  5. Crawford, D. C., Was, G. S. (1992) The role of grain boundary misorientation in intergranular cracking of Ni-16Cr-9Fe in 360掳C argon and high-purity water. Metallurgical Trans. A 23: pp. 1195-1206 CrossRef
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  7. Teng, T. L., Fung, C. P., Chang, P. H., Yang, W. C. (2001) Analysis of residual stresses and distortions in T-joint fillet welds. International Journal of Pressure Vessels and Piping 78: pp. 523-538 CrossRef
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• 刊物类别：Engineering
• 刊物主题：Mechanical Engineering
  Structural Mechanics
  Control Engineering
  Industrial and Production Engineering
  
• 出版者：The Korean Society of Mechanical Engineers
• ISSN：1976-3824

文摘

Over the last decade, primary water stress corrosion cracking (PWSCC) has been frequently found in pressurized water reactor (PWR) applications. Especially, PWSCC has occurred in long-term operated PWRs. As this phenomenon leads to serious accidents, we must be beforehand with the anticipated problems. A typical PWR consists of J-groove welded components such as reactor pressure vessel closure head and nozzles. Reactor pressure vessel closure head is made of SA508 and it is covered by cladding. Alloy 600 is used for nozzles. And J-groove weld is conducted with alloy 82/182. Different material properties of these metals lead to residual stress and PWSCC consequentially. In this study, J-groove weld residual stress was investigated by a three-dimensional finite element analysis with an actual asymmetric J-groove weld model and process of construction. Also crack growth rate of PWSCC was evaluated from cracks applied on the penetration nozzles. Based on these two values, one cannot only improve the structural integrity of PWR, but also explain PWSCC behavior such that high residual stress at the J-groove weld area causes crack initiation and propagation through the surface of nozzles. In addition, crack behavior was predicted at the various points around the nozzle.