Han-Bum Surh
Sungkyunkwan University
Displacement (fluid)Parametric statisticsSeismic loadingEngineeringGreen's functionFinite element methodLimit (mathematics)Leakage (electronics)Seismic analysisMaterials scienceConstraint (information theory)PipingContext (language use)Secondary stressLeakage ratePressure temperatureThin walledHead shapeBase isolationClosed-form expressionStress intensity factorNozzleResponse spectrumMechanicsFracture mechanicsDuctilityStructural engineeringParis' lawBendingStress (mechanics)
6Publications
1H-index
5Citations
Publications 6
Newest
#1Shin-Beom ChoiH-Index: 4
#2Han-Bum SurhH-Index: 1
Last. Jong-Wook KimH-Index: 6
view all 3 authors...
1 CitationsSource
#1Han-Bum SurhH-Index: 1
#2Shin-Beom ChoiH-Index: 4
Last. Han-Ok Ko (Korea Institute of Nuclear Safety)H-Index: 1
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Source
#1Shin-Beom ChoiH-Index: 4
#2Han-Bum SurhH-Index: 1
Last. Jong-Wook KimH-Index: 6
view all 3 authors...
1 CitationsSource
#1Han-Bum Surh (SKKU: Sungkyunkwan University)H-Index: 1
#2Tae-Young Ryu (SKKU: Sungkyunkwan University)H-Index: 2
Last. Moon Ki Kim (SKKU: Sungkyunkwan University)H-Index: 18
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Abstract In this study, the stress response of the piping system in the advanced power reactor 1400 (APR 1400) with a base isolation design subjected to seismic loading is addressed. The piping system located between the auxiliary building with base isolation and the turbine building with a fixed base is considered since it can be subjected to substantial relative support movement during seismic events. First, the support responses with respect to the base characteristic are investigated to perf...
2 CitationsSource
#1Han-Bum SurhH-Index: 1
#2Jong-Wook KimH-Index: 6
Last. Nam-Su Huh (Seoul National University of Science and Technology)H-Index: 6
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The stress intensity factor (SIF) is the major fracture mechanics parameter in LEFM concept. Since the SIF can be used for not only calculation of J-integral based on the GE/EPRI and reference stress method but also evaluation of fatigue crack growth, an accurate estimation of the SIF is an important issue for the piping in nuclear power plant. Recently, there is a need to develop the SIF solution which can cover wide geometric variables since there are on-going efforts that are developing next ...
Source
#1Min Kyu Kim (SKKU: Sungkyunkwan University)H-Index: 1
#1Min Kyu Kim (SKKU: Sungkyunkwan University)H-Index: 9
Last. Jae-Boong Choi (SKKU: Sungkyunkwan University)H-Index: 20
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Leak-before-break (LBB) is an important concept that could confirm design and integrity evaluation of nuclear power plant piping. For the LBB analysis, the detective leakage rate should be calculated for a through-wall cracked pipes. For this calculation, the crack opening displacement (COD) calculation is essential.Recently, sodium faster reactor (SFR) which has thin-walled pipes with Rm/t ranged 30–40 was introduced and then the investigation of these thin walled pipes and elbows has received ...
1 CitationsSource