• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.753-760
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• 1995

본 보고서는 영광 3,4호기 가압기 밀림관(Surge Line)에 대한 파단전누설(Leak Before Break) 개념의 적용방법, 해석절차 및 해석결과에 대하여 기술하고 있다. 영광 3,4호기 가압기 밀림관에 대한 파단전누설해석은 배관계에 대한 정적, 동적 배관해석 결과를 토대로 큰 응력 값이 작용하는 부분에 대하여 수행하였다. 가상균열의 크기는 정상운전상태에서의 하중을 이용하여 결정하였으며 격납용기에 설치된 누설감지장치의 감지능력을 1.0gpm으로 가정하였다. 영광 3,4호기 가압기 밀림관에 대한 파단전 누설해석은 NUREG 1061,Vol.3 및 SRP3.6.3에 근거하여 수행하였으며 해석결과는 동 자료에서 제시하고 있는 적용기준을 만족하고 있는 것으로 평가되었다.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.25 no.8
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• pp.1235-1241
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• 2001

An engineering estimation equation for the crack opening displacement(COD) is proposed for a complex cracked pipe, based on the reference stress approach. To define the reference stress, a simple plastic limit load analysis for the complex cracked pipe subjected 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 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.

• Journal of Ocean Engineering and Technology
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• v.15 no.2
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• pp.94-98
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• 2001

fatigue life and nondestructive evaluation were examined experimentally using surface crack specimen and compact tension specimen of 5083 aluminium alloy. Acoustic emission signals emanated during failure of aluminum alloys has been the subject of numerous investigations. Possible sources of AE during deformation have been suggested as the dislocations, fracture of brittle particles and debonding of these particles from the alloy matrix. Fatigue life and penetration behavior of long surface crack can be evaluated quantitatively using K values proposed by authors. The influence of stress ratio on the frequency characteristics of AE signals were investigated.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.28 no.5
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• pp.610-616
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• 2004

The aim of this study was to investigate the hydride embrittlement when the LBB evaluation was carried out for the integrity of PHWR Pressure Tubes. The transverse tensile and CCT toughness tests were performed at three hydrogen concentrations while the test temperatures were changed (RT to 30$0^{\circ}C$). Both the transverse tensile and the fracture toughness tests showed the hydrogen embitterment clearly at RT but this phenomenon was disappeared while the test temperature arrived at 25$0^{\circ}C$. Using the DHC test results, the CCL and LBB time were calculated and compared. The hydride embrittlement at the LBB evaluation made the LBB time short definedly. If the operating temperature, DHCV and LBB deterministic parameters such as A and m were known, LBB time could be estimated without the calculation of CCL.

• Proceedings of the KSME Conference
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• 2004.04a
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• pp.274-277
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• 2004

The most important mode of subcritical crack growth is primary water stress corrosion crack, which was the reported mechanism from the root cause analysis of the crack in the bimetallic welds. Stress corrosion crack growth evaluations was carried out for several flaw shapes of both axial and circumferential flaws, using the steady-state stresses including residual stresses. This evaluation considered the possibility of additional flaws in the primary loops of nuclear power plant, even though no such flaws have been identified by Ultrasonic Test. Consequently, Results show that the predicted flaw sizes will determine acceptability for continued service and maintenance.

• Proceedings of the KSME Conference
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• 2004.04a
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• pp.324-329
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• 2004

In this study, an application of crack morphology variables in the Leak-Before-Break(LBB) evaluation for nuclear piping systems is investigated, including influences on the leakage crack size and crack instability loads. The crack surface roughness and the number of flow turns as a function of the crack opening displacement are applied to LBB evaluations for KSNP pressurizer surge line, for which fatigue and stress corrosion cracking are considered as failure mechanisms. As a result, there would be a significant impact on safety margins to acceptance criteria for the surge line if crack morphology variables are applied additionally to the current regulatory guide without re-analyses for justification of safety factors being applied on the leakage crack size and piping loads for evaluations.

• Journal of the Korean Society of Safety
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• v.25 no.2
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• pp.7-11
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• 2010

Difficulties associated with full-scale pipe tests are rather obvious. That is, it is not only difficult to perform them but also very expensive and it requires lots of experience. And the process of the fracture test for the pipe specimen is very difficult and complicated. Because the pipe specimen, the test jig and the test equipment are very large and heavy, it requires lots of costs and times. In this study, to easily perform the fracture toughness test for a pipe specimen, load line displacement data was obtained using the image processing method.

• Nuclear Engineering and Technology
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• v.39 no.1
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• pp.75-84
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• 2007

This paper presents a closed-form model for evaluating the restraint effect of pressure induced bending on the opening of a circumferential through-wall crack, which is considered plastic deformation behavior. Three-dimensional finite element analyses with different crack lengths, restraint conditions, pipe geometries, magnitudes of internal pressure, and tensile properties were used to investigate the influence of each parameter on the pressure-induced bending restraint on the crack opening displacement. From these investigations, an analytical model based on elastic-perfectly plastic material was developed in terms of the crack length, symmetric restraint length, mean radius to thickness ratio, axial stress corresponding to the internal pressure, and normalized crack opening displacement evaluated from a linear-elastic crack opening condition. Finite element analyses results demonstrate that the proposed analytical model reliably estimated the restraint effect of pressure-induced bending on the plastic crack opening of a circumferential through-wall crack and properly reflected the dependence on each parameter within the range over which the analytical expression was derived.

• Korean Journal of Materials Research
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• v.8 no.4
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• pp.283-287
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• 1998

구미와 일본에서는 균열이 실린더벽을 과통하므로서 발생되는 일부누설로 인하여 실린더가 불안전 파괴가 이루어진 후 급속파단으로 전개되는 판당전 누설(Leak Before Break, LBB)를 전제로 한 구조건전성의 확인 시험연구가 널리 수행되고 있다. 본고에서는 Gs-C25 실린더의 구조건전성을 LBB개념의 도입과 파괴역할을 이용하여 평가하였다. 내부압력 80bar일때의 실린더에서 응력확대계수 계산은 구조물의응력확대계수가 극단적으로 큰 디멘젼을 지닌 측균열인 경우에서만 재료의 인성계수 $K_{lc}$ /와 $K_{eff}$ 에 도달된다는 것을 나타내었으며, 반면에 원주균열은 파괴 인성치 $K_{lc-}$ 와 $K_{eff-}$ 값까지는 어떠한 경우에도 도달되지 않았다. 구조물의 국부적인 취성파괴는 균열을 함유한 누설로 유도되는 범위에서, "$K_{1}$ 구조물$\geq$$K_{lc}$ 및 $K_{eff}$ "의 조건을 만족시에만 발생되며, 이는 축균열이 원주균열보다 훨씬 더 위험하다는 것을 증명한다.는 것을 증명한다.

• Nuclear Engineering and Technology
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• v.36 no.1
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• pp.112-120
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• 2004

The purpose of this paper is to analyze the piping failure frequency for the main feedwater system in domestic nuclear power plants(NPPs) for the application to an in-service inspection(ISI), leak before break(LBB) concept, aging management program(AMP), and probabilistic safety analysis(PSA). First, a database was developed for piping failure events in domestic NPPs, and 23 domestic piping failure events were collected. Among the 23 events, 12 locations of wall thinning due to flow accelerated corrosion(FAC) were identified in the main feedwater system in 4 domestic WH 3-loop NPPs. Two types of the piping failure frequency such as the damage frequency and rupture frequency were considered in this study. The damage frequency was calculated from both the plant population data and damage(s) including crack, wall thinning, leak, and/or rupture, while the rupture frequency was estimated by using both the well-known Jeffreys method and a new method considering the degradation due to FAC. The results showed that the damage frequencies based on the number of the base metal piping susceptible to FAC ranged from $1.26{\times}10^{-3}/cr.yr\;to\;3.91{\times}10^{-3}/cr.yr$ for the main feedwater system of domestic WH 3-loop NPPs. The rupture frequencies obtained from the Jeffreys method for the main feedwater system were $1.01{\times}10^{-2}/cr.yr\;and\;4.54{\times}10^{-3}/cr.yr$ for the domestic WH 3-loop NPPs and all the other domestic PWR NPPs respectively, while those from the new method considering the degradation were higher than those from the Jeffreys method by about an order of one.