Effects of Geometry of Reactor Pressure Vessel Upper Head Control Rod Drive Mechanism Penetration Nozzles on J-Groove Weld Residual Stress

Kim, Ju-Hee; Kim, Yun-Jae; Lee, Sungho; Hur, Nam-Young; Bae, Hong-Yeol; Oh, Chang-Young; Kim, Ji-Soo; Park, Heung-Bae; Lee, Seung-Geon; Kim, Jong Sung; Huh, Nam‐Su

doi:10.3795/ksme-a.2011.35.10.1337

Cited by 6 publications

(3 citation statements)

References 7 publications

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“…In order to precisely represent the real weldment procedure having 13 layers, we need, at least, 40 simulation steps because the first step is required for setting initial conditions and each weldment process has 3 steps for adding, heating, and cooling [8,9].…”

Section: Analysis Conditionmentioning

confidence: 99%

“…Since one can hardly measure residual stress distribution over the component experimentally, finite element analysis (FEA) can be alternatively performed to evaluate the residual stress caused by dissimilar J-groove weld on this PWR application [7][8][9].…”

Section: Introductionmentioning

confidence: 99%

“…Although many efforts have been conducted to evaluate the residual stress using numerical simulation, most of them were based on simplified FE models [8][9][10][11][12][13][14][15][16][17][18][19][20]. For better simulation accuracy, in this study, a 3-dimensional actual FE model of RPV closure head unit was constructed and the residual stress around the nozzle and J-groove weld was evaluated by considering the actual RPV closure head construction process.…”

Section: Introductionmentioning

confidence: 99%

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

Ryu

Park

et al. 2015

J Mech Sci Technol

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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.

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Section: Analysis Conditionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%