• 대한기계학회논문집A
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• 제36권3호
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• pp.275-282
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• 2012

본 연구에서는 탄소강 배관 재료의 동적변형시효 거동에 미치는 노치에 의한 응력과 변형 집중 효과를 파악하기 위해서, 표준 시편과 노치 시편을 이용하여 다양한 온도와 시험 속도에서 인장시험을 수행하였다. 또한, 시편의 형상에 따른 응력과 변형률 상태의 차이를 파악하기 위해서, 각 시편에 대한 유한요소 시뮬레이션을 수행하였다. 노치 시편을 이용한 인장시험 결과에서도 표준 시편에서 관찰된 것과 같은 동적변형시효의 증거인 serration과 인장강도의 증가 현상이 관찰되었다. 동일한 시험 속도에서 인장시험이 수행된 경우에 표준 시편에 비해 노치 시편에서 동적변형시효 현상이 고온에서 나타났다. 유한요소 해석 결과에 의하면 표준 시편에 비해 노치 시편에서 동적변형시효가 고온에서 나타나는 것은 노치부에서 응력과 변형의 집중으로 인한 높은 변형률 속도에 기인하는 것으로 확인되었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 춘계학술발표대회 요약집
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• pp.241.2-241.2
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• 2003

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2011년도 춘계학술대회 논문집
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• pp.1281-1282
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• 2011

• 한국산학기술학회논문지
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• 제19권9호
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• pp.20-29
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• 2018

최근 기후 및 홍수사상이 변화함에 따라 하천제방 붕괴 및 범람으로 인한 수재해 위험성이 증가하고 있는 추세이기 때문에 각종 수재해 시나리오에 대응 가능한 하천제방 유지관리 기술을 고도화할 필요가 있다. 본 논문에서는 하천제방의 효율적인 유지관리 및 재해 대응성 향상을 위하여 하천제방 안정성에 영향을 주는 주요 요소별 안전도맵 평가체계를 제안하고자 한다. 하천제방 안전도맵은 활동, 파이핑, 육안점검, 세굴, 제체재료 등의 안전도 지표를 GIS맵 상에 지도형태로 표출함으로써 육안으로 신속하게 위험지역을 파악할 수 있고, 피해발생 이후 피해복구를 실시하는 현 국내 제방관리 수준에서 벗어나 선제적인 대응을 통해 하천제방 유지관리의 효율성을 극대화 할 수 있다. 본 논문은 기 제안된 활동, 파이핑, 육안점검 등을 포함한 하천제방 안전도맵 평가체계에 세굴, 제체재료 등을 추가 및 보완한 후속논문으로서, 1)문헌 및 자료 조사를 통한 세굴 및 제체재료 3등급 기준을 제시하였으며, 시범평가를 통해 2)남강지역 좌안 5개소의 홍수위지속시간에 따른 활동 및 파이핑 특성, 3)남강지역 좌/우안 9개소의 세굴 및 제체재료 특성 등을 평가하였다. 본 논문에서 제안하는 하천제방 안전도맵 평가체계는 향후 하천관리자 행동요령, 보수 보강공법 선정, 소요 예산 산정 등을 연계한 연구가 진행된다면 보다 현실적이고, 활용성 높은 연구가 될 것으로 판단된다.

• 동력기계공학회지
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• 제5권3호
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• pp.73-79
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• 2001

The purpose of this investigation is experimentally to clarify the machinability and tool wear of STS 304 steel pipe material for piping. In order to determine the effects of cutting parameters and tool wear on thrust, torque, AE RMS, drilling is conducted on CNC milling machine. In this experiment, it is measured that thrust, torque, tool wear length, tool wear area and AE RMS during drilling using Hss tool. It has been found that a) During the drilling, the thrust and the torque of the STS 304 pipe are received more the effect of the feed than the spindle speed and the thrust increase with the increase of feed, b) The value of the AE RMS is been larger the effect of the cutting speed than the feed rate, and the value of the AE RMS increase with the increase of spindle speed, c) It has been found that the suitable feed in feed condition of 0.03, 0.05, 0.1, 0.15mm/rev is below 0.05mm/rev, d) The value of the AE RMS was shown a characteristic of the jump value during it was a sudden inrcrease of the tool wear. The increased character of the AE RMS value can be known an effective factor of the tool wear detection, and e) It can be quantitatively evaluated the condition of the tool according to calculate a area of the drill wear image which is obtained by a vision system.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 추계학술대회
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• pp.262-267
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• 2004

The unloading compliance method is the most commonly used method to evaluate the fracture resistance characteristics of a material. In dynamic loading condition, the direct current potential drop(DCPD) method has been used because the unloading compliance method can not be applied due to the discontinuity of loading. However, even in the dynamic test using DCPD method, there is a problem that the voltage drops sharply on the initiation of crack. For the reason metioned above, the normalization method was suggested on ASTM E 1820 which is revised recently, as a new method to evaluate the dynamic fracture resistance characteristic. The nomalization method can be used to obtain a fracture resistance curve directly from a load-load line displacement. In this study, we obtained two fracture resistance curves from static test of welding part of nuclear piping both by unloading compliance and nomalization method. The two curves were almost same each other, so the adaptability of the nomalization method has been proved. We conducted a dynamic fracture resistance test for the same material. The fracture resistance curve from the dynamic test was obtained by normalization method and compared to that of the static test result.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.820-830
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• 2016

Pipe wall thinning by flow-accelerated corrosion and various types of erosion is a significant and costly damage phenomenon in secondary piping systems of nuclear power plants (NPPs). Most NPPs have management programs to ensure pipe integrity due to wall thinning that includes periodic measurements for pipe wall thicknesses using nondestructive evaluation techniques. Numerous measurements using ultrasonic tests (UTs; one of the nondestructive evaluation technologies) have been performed during scheduled outages in NPPs. Using the thickness measurement data, wall thinning rates of each component are determined conservatively according to several evaluation methods developed by the United States Electric Power Research Institute. However, little is known about the conservativeness or reliability of the evaluation methods because of a lack of understanding of the measurement error. In this study, quantitative models for UT thickness measurement deviations of nuclear pipes and fittings were developed as the first step for establishing an optimized thinning evaluation procedure considering measurement error. In order to understand the characteristics of UT thickness measurement errors of nuclear pipes and fittings, round robin test results, which were obtained by previous researchers under laboratory conditions, were analyzed. Then, based on a large dataset of actual plant data from four NPPs, a quantitative model for UT thickness measurement deviation is proposed for plant conditions.

• 한국압력기기공학회 논문집
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• 제8권2호
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• pp.7-13
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• 2012

A spacer grid which is one of the most important structural components in a pressurized water reactor fuel is an interconnected array of slotted grid straps, welded at the intersections to form an egg-crate structure. The spacer grid is required to not only protect fuel rods stably but also have sufficient lateral crush strength for the sake of enabling shut-down of the nuclear reactor during abnormal operating environments. Then, the lateral crush strength of the spacer grid is closely related with welding quality of the spacer grid. Previous research on the crush strength analysis of the spacer grid had been performed using only parent material properties. In this study, to investigate the effect on the crush strength of the spacer grid when used mechanical properties in weld zone instead of parent material properties, crush strength analysis considering mechanical properties in weld zone obtained from the instrumented indentation technique was performed and compared the results with the previous research.

• 한국압력기기공학회 논문집
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• 제15권2호
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• pp.64-70
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• 2019

In recent years, attention has been paid to the integrity of steam generator (SG) tubes due to severe accident and beyond design basis accident conditions. In these transient conditions, steam generator tubes may be damaged by high temperature and pressure, which might result in a risk of fission products being released to the environment due to the failure. Alloy 690 which has increased the Cr content has been replaced for the SG tube due to its high corrosion resistance against stress corrosion cracking (SCC). However, there is lack of research on the high temperature creep rupture and life prediction model of Alloy 690. In this study, creep test was performed to estimate the high temperature creep rupture life of Alloy 690 using tube specimens. Based on manufacturer's creep data and creep test results performed in this study, creep life prediction was carried out using the Larson-Miller (LM) Parameter, Orr-Sherby-Dorn (OSD) parameter, Manson-Haford (MH) parameter, and Wilshire's approach. And a hyperbolic sine (sinh) function to determine master curves in LM, OSD and MH parameter methods was used for improving the creep life estimation of Alloy 690 material.

• 한국압력기기공학회 논문집
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• 제4권2호
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• pp.50-56
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• 2008

The tubes in heat exchanger are typically made of copper alloy, stainless steel, carbon steel, titanium alloy material. Type-439 ferritic stainless steel is ferromagnetic material, and furnish higher heat transfer rates than austenitic stainless steels and higher resistance to corrosion-induced flaws. Ferritic stainless steel can be found in low-pressure(LP) feedwater heaters and moisture separator reheaters(MSRs) in turbine system. LP feedwater heaters generally utilize thin wall Type-439 stainless steel tubing, whereas MSRs typically employ a heavier wall tubing with integral fins. Service-induced damage can occur on the O.D(outside diameter) surface of Type-439 ferritic stainless steel tubing which is employed for MSRs tubing, and the most typical damage mechanism is vibration-induced tube-to-TSP(tube support plate) wear and fatigue cracking. The wear has been reported that occurs mainly on the OD surface. Accordingly, in this study, we have evaluated the flaw sizing capability of magnetic saturation eddy current technique using magnetic saturation probe and flawed specimen.