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Dive into the research topics where Nam-Su Huh is active.

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Featured researches published by Nam-Su Huh.


International Journal of Fracture | 2001

Crack opening analysis of complex cracked pipes

Yun-Jae Kim; Nam-Su Huh; Young-Jin Kim

Based on the reference stress approach, two sets of the crack opening displacement (COD) estimation equations are proposed for a complex cracked pipe. One set of equations can be used for the case when full stress-strain data are known, and the other for the case when only yield and tensile strengths are available. To define the reference stress, a simple plastic limit analysis for the complex cracked pipe subject to combined bending and tension is performed, considering the crack closure effect in the compressive-stressed region. Comparison with ten published test data and the results from the existing method shows that the present method not only reduces non-conservatism associated with the existing method, but also provides consistent and overall satisfactory results. These results provide sufficient confidence in the use of the present method to estimate the COD (and thus the leak rate) for the Leak-before-Break (LBB) analysis of complex cracked pipes. Finally, the J-estimation equations are also provided for complex cracked pipes, for the LBB analysis of complex cracked pipes.


Journal of Pressure Vessel Technology-transactions of The Asme | 2004

Prediction of Failure Behavior for Nuclear Piping Using Curved Wide-Plate Test

Nam-Su Huh; Yun-Jae Kim; Jae-Boong Choi; Young-Jin Kim; Chang-Ryul Pyo

One important element of the Leak-Before-Break analysis of nuclear piping is how to determine relevant fracture toughness (or the J-resistance curve) for nonlinear fracture mechanics analysis. The practice to use fracturetoughness from a standard C(T) specimen is known to often give conservative estimates of toughness. To improve the accuracy of predicting piping failure, this paper proposes a new method to determine fracture toughness using a nonstandard testing specimen, curved wide-plate in tension. To show validity of the proposed curved wide-plate test, the J-resistance curve from the full-scale pipe test is compared with that from the curved wide-plate test and that from C(T) specimen. It is shown that the J-resistance curve from the curved wide-plate tension test is similar to, but that from the C(T) specimen is lower than, the J-resistance curve from the full-scale pipe test. Further validation is performed by investigating crack-tip constraint conditions via detailed three-dimensional finite element analyses, which shows that the crack-tip constraint condition in the curved wide-plate tension specimen is indeed similar to that in the full-scale pipe under bending.


Nuclear Engineering and Design | 1999

Development of modified piping evaluation diagram for leak-before-break application to Korean next generation reactor

Yun-Jae Kim; Youn-Jung Lee; Nam-Su Huh; C.R. Pyo; Jun-Seok Yang

Abstract Recently, the piping evaluation diagram (PED) is accepted in nuclear industry for an efficient application of leak-before-break (LBB) concept to piping system at an initial piping design stage. The objective of this paper is to develop the modified PED, which can account for the variation of the material properties of the PED development stage and those of the assembly stage. For this purpose, a parametric study was performed to investigate the effect of stress–strain curve on the detectable leakage crack length and the effect of fracture resistance curve on the LBB allowable load. Finite element analyses were also performed to investigate the effect of stress–strain curve on the LBB allowable load. Finally, a modified PED was proposed as a function of crack length and the allowable safe shutdown earthquake load. The LBB analyses based on the modified PED are in good agreement with those based on the traditional PED. By adopting the modified PED, the variation of material properties can be considered in the LBB analysis and the computing times required for the application of LBB during the design process can be considerably reduced.


Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management | 2006

Failure Pressure Estimates of Steam Generator Tubes Containing Wear-Type Defects

Yoon-Suk Chang; Jong Min Kim; Nam-Su Huh; Young-Jin Kim; Seong Sik Hwang; Joung-Soo Kim

It is commonly requested that steam generator tubes with defects exceeding 40% of wall thickness in depth should be plugged to sustain all postulated loads with appropriate margin. The critical defect dimensions have been determined based on the concept of plastic instability. This criterion, however, is known to be too conservative for some locations and types of defects. In this context, the accurate failure estimation for steam generator tubes with a defect draws increasing attention. Although several guidelines have been developed and are used for assessing the integrity of defected tubes, most of these guidelines are related to stress corrosion cracking or wall-thinning phenomena. As some of steam generator tubes are also failed due to fretting and so on, alternative failure estimation schemes for relevant defects are required. In this paper, three-dimensional finite element (FE) analyses are carried out under internal pressure condition to simulate the failure behavior of steam generator tubes with different defect configurations; elliptical wastage type, wear scar type and rectangular wastage type defects. Maximum pressures based on material strengths are obtained from more than a hundred FE results to predict the failure of the steam generator tube. After investigating the effect of key parameters such as wastage depth, wastage length and wrap angle, simplified failure estimation equations are proposed in relation to the equivalent stress at the deepest point in wastage region. Comparison of failure pressures predicted according to the proposed estimation scheme with some corresponding burst test data shows good agreement, which provides a confidence in the use of the proposed equations to assess the integrity of steam generator tubes with wear-type defects.Copyright


Fatigue & Fracture of Engineering Materials & Structures | 2001

Enhanced reference stress-based J and crack opening displacement estimation method for leak-before-break analysis and comparison with GE/EPRI method

Yun Jae Kim; Nam-Su Huh


Fatigue & Fracture of Engineering Materials & Structures | 2007

Elastic-plastic fracture mechanics assessment for steam generator tubes with through-wall cracks

Nam-Su Huh; Jong-Min Kim; Yoon-Suk Chang; Young-Jin Kim; Seong-Sik Hwang; Joung-Soo Kim


Fatigue & Fracture of Engineering Materials & Structures | 2001

Effect of Lüders strain on engineering crack opening displacement estimations for leak-before-break analysis: finite element study

Yun Jae Kim; Nam-Su Huh


Nuclear Engineering and Design | 2007

Coalescence evaluation of collinear axial through-wall cracks in steam generator tubes

Yoon-Suk Chang; Nam-Su Huh; Young-Jin Kim; Jin Ho Lee; Young-Hwan Choi


Jsme International Journal Series A-solid Mechanics and Material Engineering | 2005

Engineering J Estimation Methods for Leak-Before-Break Analyses of Nuclear Piping

Y.-J. Kim; Nam-Su Huh; Young-Jin Kim


Fatigue & Fracture of Engineering Materials & Structures | 2003

Estimations of creep fracture mechanics parameters for through‐thickness cracked cylinders and finite element validation

Yun Jae Kim; Nam-Su Huh

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Yun-Jae Kim

Sungkyunkwan University

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Jun-Seok Yang

Electric Power Research Institute

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Jin Ho Lee

Korea Institute of Nuclear Safety

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Jong-Min Kim

Sungkyunkwan University

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