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김유영,Kim Sung Hwan,김태범,Yun Young Sun,Shin Jung Im,Oh Il Young,Sir Jung Ju,김경묵,박혜경,강혜련,장윤석,최동철,송영욱,김윤근,민경업,조상헌 대한의학회 2005 Journal of Korean medical science Vol.20 No.4
We report here a case with hypereosinophilia and peripheral artery occlusion. A 32-yr-old Korean woman presented to us with lower extremity swelling and pain. Angiography revealed that multiple lower extremity arteries were occlusive. The biopsy specimen showed perivascular and periadnexal dense eosinophilic infiltration in dermis and subcutaneous adipose tissue. Laboratory investigations revealed a persistent hypereosinophilia. She was prescribed prednisolone 60 mg daily. Her skin lesion and pain were improved and the eosinophil count was dramatically decreased. After discharge, eosinophil count gradually increased again. Cyanosis and pain of her fingers recurred. She had been treated with cyclophosphamide pulse therapy. Her eosinophilia was decreased, but the cyanosis and tingling sense were progres-sive. The extremity arterial stenoses were slightly progressed. Skin biopsy showed perivascular eosinophilic infiltration in the dermis and CD40 ligand (CD40L) positive eosinophilic infiltration. The serum TNF- was markedly increased. These results suggest that CD40L (a member of TNF- superfamily) could play a role in the inflam-matory processes when eosinophil infiltration and activation are observed. We pre-scribed prednisolone, cyclophosphamide, clopidogrel, cilostazol, beraprost and nifedipine, and she was discharged.
THE EFFECT OF POSTULATED FLAWS ON THE STRUCTURAL INTEGRITY OF RPV DURING PTS
정명조,YOUNG HWAN CHOI,장윤석,JONG-WOOK KIM 한국원자력학회 2007 Nuclear Engineering and Technology Vol.39 No.5
Postulation of flaws, one of the most important areas in RPV integrity assessment, significantly affects the results. In the present work, several parameters, such as orientation, underclad vs. surface cracking, crack depth and shape, etc., are postulated and parametric studies are performed to investigate the influence of the flaw parameters on the structural integrity assessment of the reactor pressure vessel during pressurized thermal shock. The influence of individual parameters describing the crack is evaluated based on sensitivity study results.
김영환,박은정,장윤석 ( Young Hwan Kim,Eun Jung Park,Yoon Seok Chang ) 생화학분자생물학회 1994 BMB Reports Vol.27 No.6
After horse heart cytochrome C was digested enzymatically with trypsin, the mixture of digestion solution was separated by gradient reverse-phase HPLC and collected fractionally. Using electrospmy ionization mass spectrometry (ESI-MS), each peptide was analyzed for exact molecular mass. The sequence informations for some tryptic peptides were obtained by cone voltage fragmentation method. These results suggest that mass spectrometry can be used to sequence peptides or proteins, to define N- and C-terminal sequence heterogenity, to locate and to correct errors in DNA- and cDNA-deduced protein sequences, which are not easily handled by conventional techniques.
CANDU 원전 주요기기에 대한 웹기반 경년열화 평가 시스템 개발
고한옥(Han-Ok Ko),장윤석(Yoon-Suk Chang),최재붕(Jae-Boong Choi),김영진(Young-Jin Kim),최영환(Young-Hwan Choi) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
A couple of years ago, in Korea, Periodic Safety Review (PSR) was adopted in order to assure the continued safe operation of nuclear power plants. The PSR considering various aging effects is being performed every ten-years in general and, for this, complicated procedures are required such as inspection, structure analysis, failure assessment and combination of them. A Web-based Regulatory Aging Assessment Program (CANDU-RAAP) is proposed in this paper, which manages key operating data efficiently and assists effective evaluation of major components consisting CANDU type nuclear power plant. By using the proposed program, experts in different fields can co-operate to resolve industrial issues and all users can share informations and create valuable knowledge-base.
문성인(Seong-In Moon),장윤석(Yoon-Suk Chang),김영진(Young-Jin Kim),이진호(Jin-Ho Lee),송명호(Myung-Ho Song),최영환(Young-Hwan Choi),황성식(Seong-Sik Hwang) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.8
The 40% of wall thickness criterion, which is generally used for the plugging of steam generator tubes, is applied only to a single crack. In the previous study, a total number of 10 local failure prediction models were introduced to estimate the coalescence load of two collinear through-wall cracks and the reaction force model and plastic zone contact model were selected as optimum ones. The objective of this study is to estimate the coalescence load of two collinear through-wall cracks in steam generator tube by using the optimum local failure prediction models. In order to investigate the applicability of the optimum local failure prediction models, a series of plastic collapse tests and corresponding finite element analyses for two collinear through-wall cracks in steam generator tube were carried out. Thereby, the applicability of the optimum local failure prediction models was verified and finally a coalescence evaluation diagram which can be used to determine whether the adjacent cracks detected by NDE coalesce or not was developed.
우승완(Seung-Wan Woo),장윤석(Yoon-Suk Chang),최재붕(Jae-Boong Choi),김영진(Young-Jin Kim),정명조(Myung-Jo Jhung),최영환(Young-Hwan Choi) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.5
The well-known flaw evaluation criteria embodied in ASME Sec. XI are not applicable to secondary system piping of nuclear power plants, mainly, due to different R/t ratios comparing with those of primary system piping. Despite of previous activities to resolve this specific issue, there are still arguments to determine whether flaws detected in the secondary system are acceptable or not for continued service. In the present study, pros and cons of relevant researches are fully discussed and unique features of secondary system piping are assessed by retrieving a database enveloping eight nuclear power plants. Subsequently, for pipe geometries beyond the ASME applicable limits, finite element analyses are carried out by changing sizes of surface crack. The analysis results showed limitations of current flaw evaluation schemes and addressed necessity of establishing a new one which will be available from further detailed finite element analyses.
Seong Wook Sohn,장윤석,이혜승,정두현,이춘택,Young Hwan Kim,김윤근,민경업,김유영,조상헌 대한의학회 2008 Journal of Korean medical science Vol.23 No.3
The bronchial pathology of asymptomatic airway hyperreponsiveness (AHR) subjects is not well understood, and the role of atopy in the development of airway remodeling is unclear. The aim of this study was to evaluate whether atopy is associated with airway remodeling in asymptomatic AHR subjects. Five groups, i.e., atopic or non-atopic subjects with asymptomatic AHR, atopic or non-atopic healthy controls, and subjects with mild atopic asthma, were evaluated by bronchoscopic biopsy. By electron microscopy, mean reticular basement membrane (RBM) thicknesses were 4.3±1.7 ㎛, 3.4±1.8 ㎛, 2.5±1.5 ㎛, 2.6±1.1 ㎛, and 2.3±1.2 ㎛ in the mild atopic asthma, atopic and non-atopic asymptomatic AHR, atopic and nonatopic control groups, respectively (p=0.002). RBM thicknesses were significantly higher in the mild atopic asthma group and in the atopic asymptomatic AHR group than in the other three groups (p=0.048). No significant difference in RBM thickness was observed between the atopic asymptomatic AHR group and the mild atopic asthma group (p>0.05), nor between non-atopic asymptomatic AHR group and the two control groups (p>0.05). By light microscopy, subepithelial layer thicknesses between the groups showed the same results. These findings suggest that RBM thickening occurs in subjects with atopic asymptomatic AHR, and that atopy plays an important role in airway remodeling.
안민용(Min-Yong Ahn),배성렬(Sung-Ryul Bae),박영재(Young-Jae Park),장윤석(Yoon-Suk Chang),최재붕(Jae-Boong Choi),김영진(Young-Jin Kim),정명조(Myung-Jo Jhung),최영환(Young-Hwan Choi) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.11
In general, major components of nuclear power plant have been evaluated based on 2-dimensional design codes conservatively. However, more exact assessment is necessary for continued operation beyond the design life. In this paper, 3-dimensional stress and fatigue analyses reflecting full geometry and monitored operating condition of reactor pressure vessel have been carried out. The analyses results showed that conservatism of current 2-dimensional evaluation based on design transient. Therefore, it is anticipated that the schemes developed from this research such as 3-dimensional finite element modeling, stress analysis and fatigue analysis related techniques can be utilized as fundamental tools for exact lifetime evaluation and license renewal of major nuclear components.