• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.11 no.2
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• pp.25-30
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• 2015

In the present study, complex leakage probabilities of nuclear pipes due to fatigue and stress corrosion cracking are evaluated by using the PINTIN(Piping INTegrity INner flaws) that is developed based on the existing PRAISE(Piping Reliability Analysis Including Seismic Events) program. With regard to the aging and crack instability, small leak and big leak probabilities are calculated for several pipes in a reactor coolant system of domestic nuclear plant. Moreover, sensitivity analysis is also performed to find out the effect of parameters for the leakage of pipes, which shows the coolant temperature is the most influencing parameter.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.515-520
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• 1996

원자력 발전소 증기발생기의 1차측 및 2차측 응력부식균열에 대한 온도감소 효과를 고리 1호기의 현장 데이터를 근간으로 분석하였다. 고리 1호기의 경우 출력을 100%에서 85%로 감소시키므로써, 고온관 온도는 320.5$^{\circ}C$에서 313.5$^{\circ}C$로 7$^{\circ}C$ 감소하였으며, 이와 같은 온도감소 효과로 PWSCC 손상률은 약 40%, ODSCC 손상률은 약 33% 감소하는 것으로 산출되었다. PWSCC의 경우 Weibull 기울기는 b = 5.6 에서 b : 3.8로 감소한 것으로 나타났다. PWSCC의 억제방안으로는 출력감발에 의한 온도감소가 가장 효과적이지만, ODSCC의 경우에는 틈새 분위기의 변환이 큰 역할을 하는 것으로 나타났다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.469-474
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• 1996

Alloy 690은 응력부식 균열에 대한 저항성이 요구되는 원자력 발전소 증기발생기 전열관 재료에 사용되고 있다$^{(1)}$ . 응력부식 균열에 대한 저항성은 주로 결정입계에 존재하는 크롬탄화물의 기여에 의한 것이 대부분이다. 크롬탄화 석출물의 핵생성을 알아보기 위해서 110$0^{\circ}C$에서 용체화처리를 0, 1, 3, 10분 동안 하여 관찰하였다. 용체화처리한 모든 시편에서 결정입계에 존재하는 석출물의 분포는 쌍정과 교차하면서 갑자기 변화하는 것을 관찰 할 수 있다. 이처럼 석출물이 존재하지 않는 결정입계들은 대부분 낮은 ∑ 값의 CLS으로부터 약간 벗어난 입계가 될 것이다. 결정입계에 존재하는 석출물은 기지와 Cube-Cube orientation relationship을 갖는다. 그리고 단지 하나의 결정입과 반정합을 이룬다. 기지와 반정합을 이루는 석출물은 M$_{23}$ C$_{6}$형태의 크롬 탄화물이고 격자상수는 기지의 격자상수보다 3배 크다.

• Journal of the Korean Society of Manufacturing Process Engineers
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• v.6 no.2
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• pp.34-40
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• 2007

Antifatigue failure technology take an important part of current industries. Currently, the shot peening is used for removing the defect from the surface of steel and improving the fatigue strength on surface. Therefore, this paper the effect of compressive residual stress and corrosion of spring steel(SAE 5155)by shot-peening on fatigue crack growth characteristics in stress ratio(R=0.05)was investigated with considering fracture mechanics. By using the methods mentioned above, We arrived at the following conclusions. The fatigue crack growth rate(da/dN) of the shot-peening material was lower than that of the un-peening material. And in stage I, ${\Delta}Kth$, the threshold stress intensity factor, of the shot-peen processed material is high in critical parts unlike the un-peening material. Also m, fatigue crack growth exponent and number of cycle of the shot-peening material was higher than that of the un-peening material. That is concluded from effect of da/dN. Finally fracture of shot-peening material and un-peening material was identified and discussed in this study.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.20 no.1
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• pp.25-31
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• 2024

The core shroud of rector vessel internals (RVI) of OPR1000 and ARP1400 is made of Type 304 stainless steel (SS) by bending and welding process that may induce high deformation and residual stress in manufacturing. This work aims to evaluate the susceptibility of stress corrosion crack (SCC) initiation of bent parts of RVI in high temperature primary water environment. For SCC initiation test, tensile specimens were fabricated from the 90 degree bent plate of Type 304 SS (DT specimen), that is an archived part of a Korean APR1400. After the SCC initiation test, the specimen surface was thoroughly examined by optical and scanning electron microscopy, and compared to the specimen fabricated from the as-received plate of Type 304 SS (AR specimen). The surface observation revealed that SCC initiated on the AR specimen surface in typical intergranular (IG) mode, while SCC on the DT specimen occurred in transgrannular mode as well as IG mode. It was also found that the size and number of SCC on the DT specimen were larger than that on the AR specimen. This was attributable to a strain-hardening during the bending process. To compare the susceptibility of SCC initiation, total crack density (TCD) was calculated from the total crack length divided by the measured area of AR and DT specimens. TCD of DT specimen was 4.6 times higher than AR specimen in average, indicating that higher possibility of degradation of bent parts of RVI for a long-term operation.

• Proceedings of the KWS Conference
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• 1993.05a
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• pp.107-110
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• 1993

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.295.2-295
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• 2001

• Proceedings of the Materials Research Society of Korea Conference
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• 1995.11a
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• pp.121-121
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• 1995

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.237-237
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• 1998

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.244-244
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• 1998