• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.9 no.1
• /
• pp.56-61
• /
• 2013

This paper presents the results of integrity assessment for the cracks happened in reactor vessel upper head penetration nozzles. The crack morphology for a boat sample from crack area was analyzed through microscope. The stress condition including weld residual stress around crack was analyzed using finite element analysis. From the results of crack morphology and stress condition, the crack was concluded as primary water stress corrosion cracking. The integrity of the cracked nozzle was assessed by the methodology provided in ASME Section XI. According to the assessment results, the remaining life of the cracked nozzle was 1.43 yrs. and the plant decided to repair it.

• Korean Journal of Materials Research
• /
• v.11 no.4
• /
• pp.266-271
• /
• 2001

Effect of Cd addition on the stress corrosion cracking(SCC) resistance of Al-Cu-Mn cast alloy was investigated by C-ring test and electrical conductivity measurement. With increasing Cd contents, the electrical conductivity and the SCC resistance were increased. The PFZ and coarse precipitates along the grain boundary were observed from TEM micrographs. The fracture made of the alloys was confirmed as intergranular type and showed brittle fracture surface. As a result, it was concluded that the SCC mechanism of these alloys is the anodic dissolution model. The maximum hardness was increased from 127Hv in the Cd-free alloy to 138∼145Hv in the Cd addition alloys.

• Journal of the Korean institute of surface engineering
• /
• v.36 no.4
• /
• pp.301-306
• /
• 2003

Multilayered WC-Ti/suv $1-x/Al_{x}$ N coatings were deposited on AISI D2 steel using cathodic arc deposition (CAD) method. These coatings contain structural defects such as pores or droplets. Thus, the substrate is not completely isolated from the corrosive environment. The growth defects (pores, pinholes) in the coatings are detrimental to corrosion resistance of the coatings used in severe corrosion environments. The localized corrosion behavior of the coatings was studied in deaerated 3.5 wt.% NaCl solution using electrochemical techniques (potentiodynamic polarization test) and surface analyses (GDOES, SEM, AES, TEM). The porosity was calculated from the result of potentiodynamic polarization test of the uncoated and coated specimens. The calculated porosity is higher in the $WC-Ti_{0.6}$ $Al_{0.4}$ N than others, which is closely related to the packing factor. The positive effects of greater packing factor act on inhibiting the passage of the corrosive electrolyte to the substrate and lowering the localized corrosion kinetics. From the electrochemical tests and surface analyses, the major corrosion mechanisms can be classified into two basic categories: localized corrosion and galvanic corrosion.

• Transactions of the Korean Society of Mechanical Engineers A
• /
• v.39 no.4
• /
• pp.405-413
• /
• 2015

In the US, the number of cases of subterranean water contamination from tritium leaking through a damaged buried nuclear power plant pipe continues to increase, and the degradation of the buried metal piping is emerging as a major issue. A pipe blocked from corrosion and/or degradation can lead to loss of cooling capacity in safety-related piping resulting in critical issues related to the safety and integrity of nuclear power plant operation. The ASME Boiler and Pressure Vessel Codes Committee (BPVC) has recently approved Code Case N-755 that describes the requirements for the use of polyethylene (PE) pipe for the construction of Section III, Division 1 Class 3 buried piping systems for service water applications in nuclear power plants. This paper contains tensile and slow crack growth (SCG) test results for high-density polyethylene (HDPE) pipe welds under the environmental conditions of a nuclear power plant. Based on these tests, the fracture surface of the PENT specimen was analyzed, and the fracture mechanisms of each fracture area were determined. Finally, by using 3D finite element analysis, limit loads of HDPE related to premature failure were verified.

• Journal of the Korean Society for Nondestructive Testing
• /
• v.29 no.4
• /
• pp.374-382
• /
• 2009

Steam generator(SG) tube, as a barrier isolating primary to the secondary coolant system of nuclear power plants(NPP), must maintain the structural integrity far the public safety and its efficient power generation capacity. And SG tubes bearing defects must be timely detected and taken repair measures if needed. For the accomplishment of these objectives, SG tubes have been periodically examined by eddy current testing(ECT) on the basis of administrative notices and intensified SG management program(SGMP). Stress corrosion cracking(SCC) on the SG tubes is not easily detected and even missed since it has lower signal amplitude and other disturbing factors against its detection. However once SCC is developed, that can cause detrimental affects to the SG tubes due to its rapid propagation rate. Accordingly SCC is categorized as prime damage mechanism challenging the soundness of the SG tubes. In this study, reproduced EDM notch specimens are examined for the detectability and quantitative characterization of the axial ODSCC by +PT MRPC probe, containing pancake, +PT and shielded pancake coils apart in a single plane around the circumference. The results of this study are assumed to be applicable fur providing key information of engineering evaluation of SCC and improvement of confidence level of ECT on SG tubes.

• Journal of Energy Engineering
• /
• v.27 no.2
• /
• pp.1-13
• /
• 2018

The proportion of natural gas-fueled power generation is expanding due to the change of domestic energy policy pursuing reduction of dust and increasing clean energy consumption. Natural gas fuels used for the combined-cycle power plants and the district-heating power plants are operated at high temperature and high pressure in the fuel supply system. Accidents due to leakage of the gas such as fire and explosion should be prevented by applying risk management techniques. In this study, risk assessment was performed on the natural gas fuel supply system of a combined power plant based on the API RP 581 RBI code. For the application of the API RBI code, lines and segments of the evaluation target system were identified. Operational data and input information were analyzed for the calculations of probability of failure and consequence of failure. The results of the risk assessment were analyzed over time from the initial installation time. In the code-based evaluation, the gas fuel supply system was mainly affected by thinning, external damage, and mechanical fatigue damage mechanisms. As the operating time passes, the risk is expected to increase due to the external damage caused by the CUI(Corrosion Under Insulation).

• Proceedings of the Korea Water Resources Association Conference
• /
• 2009.05a
• /
• pp.1494-1498
• /
• 2009

세계기상기구(WMO)에 의하여 홍수예경보시스템의 평가를 위하여 개발된 MOFFS Ver.3의 개선을 위하여 특정유역의 홍수방어체계의 취약성을 평가하고 홍수방어시스템의 완성도를 높이기위한 DSS-FOP를 개발하였다. DSS-FOP는 지점별, 홍수사상별로 예보시스템 운영결과를 간단한 평가양식에 나타내는 시스템이며, 홍수방어구조물(Flood control infra)과 홍수조절운영(Flood control operation)으로 분류한다. 홍수방어구조물은 수문관측, 홍수방어구조물, 홍수조절지휘소로, 홍수조절 운영은 자료처리 및 전송, 홍수예측모형, 예경보발령의 총 6가지 주요평가항목과 하부의 23가지 세부평가항목으로 구성하였다. 점수부여체계는 최대점수, 목표점수, 성과점수, 부족점수, 취약점수의 산정을 통하여 구조물인프라와 운영측면에서의 시스템취약부분을 평가 진단할 수 있도록 하였다. 개발된 DSS-FOP를 이용하여 국내의 한강유역과 UN/ESCAP 태풍위원회의 회원국인 태국의 Khlong U-Taphao 유역을 대상으로 적용하고 그 결과를 비교 평가하였다. 한강유역의 경우 하천정보센터 신설 및 조직강화로 인적자원측면에서 높은 성과점수를 보였으며, 향후 수문레이더 설치 등으로 관측분야에서의 개선이 기대된다. 태국의 Khlong U-Taphao 유역의 경우 목표수준을 다소 조정할 필요가 있으며, 비상행동계획의 마련이 시급하다. 더불어 홍수방어구조물에 대한 지속적인 투자가 필요한 상황이다. 이러한 DSS-FOP의 평가결과는 국가별, 유역별, 호우사상별로 관리되며, 태풍위원회 회원국의 적용 및 기술지침의 작성을 위해 많은 평가 및 조사가 축적되어야 한다.

• Transactions of the Korean Society of Mechanical Engineers A
• /
• v.36 no.10
• /
• pp.1235-1239
• /
• 2012

Primary water stress corrosion cracking (PWSCC) has been observed around the weld region of control rod drive mechanism (CRDM) nozzles in nuclear power plants overseas. The weld has a J-shaped groove and it connects the CRDM nozzle with the reactor vessel upper head (RVUH). It is a dissimilar metal weld (DMW), because the CRDM is made of alloy 600 and the RVUH is made of carbon steel. In this study, finite element analysis (FEA) was performed to estimate the stress condition around the weld region. Generally, it is known that a high tensile region is more susceptible to PWSCC. FEA was performed as for the condition of welding, hydrostatic test and normal operation successively to observe how the residual stress changes due to plant condition. The FEA results show that a high tensile stress region is formed around the weld starting point on the inner surface and around the weld stop point on the outer surface.

• KSCE Journal of Civil and Environmental Engineering Research
• /
• v.7 no.1
• /
• pp.93-101
• /
• 1987

Residual stresses have remained around welding areas of a steel structure member after welding operation. The major causes to occur these residual stresses are the local heat due to a welding, the heat stresses due to a irregular and rapid cooling condition, the material and rigidity of a steel structure. Ultimatly, these residual stresses have been known to decrease a brittle fracture strength, a fatigue strength, a buckling strength, dynamic properties, and the corrosion resistance of the material. This paper deals with the residual stresses on a steel structure member through experimental studies. SWS 58 plates were welded by the method of X-groove type. These plates were layed on the heat treatment at four different temperatures; $350^{\circ}C$, $500^{\circ}C$, $650^{\circ}C$ and $800^{\circ}C$. The resulting residual Stresses were measured by hole drilling method, and the followings were obtained. The residual stresses on the vicinity of a welding point were relieved most effectively at the temperature of $650^{\circ}C$, and these stresses relieved completly when the ratio of a hole diamerter to a hole depth became unity. Hardness test shows that the higher value of hardness at the heat affected zone dropped to belower as the temperature went up from $350^{\circ}C$ to $800^{\circ}C$. The Welding input heats have not influenced the magnitude of residual stresses at the input heat range between above and below one forth than standard.

• Journal of Food Hygiene and Safety
• /
• v.3 no.3
• /
• pp.117-129
• /
• 1988

Packaged meal manufacturing establishments in Seoul city and Kyungkido province were assessed in terms of the sanitary conditions and practices, time and temperature, and microbiological quality. Sanitary check-lists were developed to evaluate the sanitary condition of sampled packaged meal manufacturing establishments. Microbiological tests on.food containers, equipments, and foods in various phases of product flow were done. The results of the study are summarized as follows; 1) Sanitary condition of kitchen.and sanitary practices of employees in.large and medium establishments were evaluated as the some improvement required in order to meet all standards. But sanitary practices of employees in small establishments were evaluated as the unsatisfactory state with negligence or ignorance of safe practice. 2) The microbiological quality of basic ingredients and food materials after pre-preparation were poor. 3) Time and temperature data indicated that phases of holding ingredients at room temperature after cooking, assembly and packaging before delivery were critical. 4) Microbiological test results for food containers, equipments indicated that sanitary conditions of stainless steel ware, knife, wiping clothes and cutting board should be improved promptly. 5) Critical control points identified were ingredients, pre-preparation, Holding, and assembly and packaging. 6) Guidelines were suggested for effective quality control of packaged meals production.