• Journal of Chest Surgery
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• 제22권2호
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• pp.348-356
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• 1989

Seventeen patients of pulmonary atresia with intact ventricular septum were underwent operation during 4.8years period from Jan. 1983 to Aug. 1988 at Seoul National university Hospital. The patients were composed of 8 males and 9 females, aging 1day to 2.5 years [mean 88 days]. We classified pulmonary atresia according to right ventricular morphology; those with tripartite ventricles in 12, those with no trabecular portion to the cavity in 0, and those with inlet portion only in 5. The tripartite approach to right ventricular morphology is helpful in selecting the type of initial palliative procedures. Palliative procedures were as follows; pulmonary valvotomy in 5 with 3 early survivors, mod B-T shunt in 4 with 3 early survivors, and palliative right ventricular outflow tract reconstruction in 4 with 1 early survivor. Effective preliminary palliation of pulmonary atresia are pulmonary valvotomy or palliative right ventricular outflow tract reconstruction in those with tripartite right ventricle, and modified Blalock-Taussig shunt in those with no infundibular portion. The approach to definitive repair is based primarily on the actual size of the tricuspid annulus and the right ventricular cavity. Definitive repair was as follows: definitive right ventricular outflow tract reconstruction in 4 with all survivors and mod. Fontan operation in 2 with one survivors. Right ventricular outflow tract reconstruction can be done as complete repair for patients who had adequate tricuspid annulus and right ventricular cavitary size and mod. Fontan operation for patients who severely hypoplastic tricuspid valve annulus or small right ventricular cavity.

• Nuclear Engineering and Technology
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• 제27권5호
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• pp.710-720
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• 1995

원자로에서 펌프에 의해 야기되는 맥동 압력은 원자로 내부 구조물에 진동과 손상을 줄 수 있기 때문에 관심이 증가되고 있다. 본 연구에서는 냉각관과 환형관(원자로 압력 용기와 노심 보호 지지대 사이)으로 구성된 기하 형태에서 펌프에 의해 야기되는 맥동 압력을 해석할 수 있는 수력학적 모델을 개발하였다. 수학적 지배 방정식은 압축성, 비점성 유체에 대해 선형화된 Navier-Stokes 방정식이다. 냉각관과 환형관을 따로 분리하여 해석하고 두영역의 커플링 영향을 고려하였다. 또한 본 기하 형태에서 펌프맥동 압력에 영향을 미치는 주요 기하 인자에 대한 평가를 수행하였다. 본 해석 결과와 실험차를 비교하여 만족할 만한 결과를 얻었다.

• Journal of Mechanical Science and Technology
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• 제17권8호
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• pp.1171-1184
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• 2003

An experimental study on critical heat flux (CHF) has been performed in an internally heated vertical annulus with non-uniform heating. The CHF data for the chopped cosine heat flux have been compared with those for uniform heat flux obtained from the previous study of the authors, in order to investigate the effect of axial heat flux distribution on CHF. The local CHF with the parameters such as mass flux and critical quality shows an irregular behavior. However, the total critical power with mass flux and the average CHF with critical quality are represented by a unique curve without the irregularity. The effect of the heat flux distribution on CHF is large at low pressure conditions but becomes rapidly smaller as the pressure increases. The relationship between the critical quality and the boiling length is represented by a single curve, independent of the axial heat flux distribution. For non-uniform axial heat flux distribution, the prediction results from Doerffer et al.'s and Bowling's CHF correlations have considerably large errors, compared to the prediction for uniform heat flux distribution.

• Nuclear Engineering and Technology
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• 제40권2호
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• pp.155-162
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• 2008

Heat transfer experiments in an annulus passage were performed using SPHINX(Supercritical Pressure Heat Transfer Investigation for NeXt Generation), which was constructed at KAERI(Korea Atomic Energy Research Institute), to investigate the heat transfer behaviors of supercritical $CO_{2}$. $CO_{2}$ was selected as the working fluid to utilize its low critical pressure and temperature when compared with water. The mass flux was in the range of 400 to 1200 $kg/m^{2}s$ and the heat flux was chosen at rates up to 150 $kW/m^{2}$. The selected pressures were 7.75 and 8.12 MPa. At lower mass fluxes, heat transfer deterioration occurs if the heat flux increases beyond a certain value. Comparison with the tube test results showed that the degree of heat transfer deterioration in the heat flux was smaller than that in the tube. In addition, the Nusselt number correlation for a normal heat transfer mode is presented.

• Nuclear Engineering and Technology
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• 제34권4호
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• pp.382-395
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• 2002

An experimental study on transient critical heat flux (CHF) under flow coastdown has been performed for the water flow in a non-uniformly heated vertical annulus under low flow and a wide range of pressure conditions. The objectives of this study are to systematically investigate the effect of the flow transient on the CHF and to compare the transient CHF with steady-state CHF The transient CHF experiments have been performed for three kinds of flow transient modes based on the coastdown data of a nuclear power plant reactor coolant pump. At the same inlet subcooling, system pressure and heat flux, the effect of the initial mass flux on the critical mass flux can be negligible. However, the effect of the initial mass flux on the time-to- CHF becomes large as the heat flux decreases. The critical mass flux has the largest value for slow flow reduction rate. There is a pressure effect on the ratio of the transient CHF data to steady-state CHF data. Except under low system pressure conditions, the flow transient CHF was revealed to be conservative compared with the steady-state CHF data. Bowling CHF correlation and thermal hydraulic system code MARS show promising results for the prediction of CHF occurrence .

• Geomechanics and Engineering
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• 제16권6호
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• pp.619-626
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• 2018

A simple prediction procedure was investigated for calculating the stresses and displacements of a circular opening. Unlike existed approaches, the proposed approach starts each step with a radius increment. The stress for each annulus could be obtained analytically, while strain increments for each step can be determinate numerically from the compatility equation by finite difference approximation, flow rule and Hooke's law. In the successive manner, the distributions of stresses and displacements could be found. It should be noted that the finial radial stress and displacement were equal to the internal supporting pressure and deformation at the tunnel wall, respectively. By assuming different plastic radii, GRC and the evolution curve of plastic radii and internal supporting pressures could be obtained conveniently. Then the real plastic radius can be calculated by using linear interpolation in the evolution curve. Some numerical and engineering examples were performed to demonstrate the accuracy and validity for the proposed procedure. The comparisons results show that the proposed procedure was faster than that in Lee and Pietrucszczak (2008). The influence of annulus number and dilation on the accuracy of solutions was also investigated. Results show that the larger the annulus number was, the more accurate the solutions were. Solutions in Park et al. (2008) were significantly influenced by dilation.

• Clinical and Experimental Pediatrics
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• 제63권5호
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• pp.189-194
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• 2020

Background: The decision to use transannular patching (TAP) during tetralogy of Fallot (TOF) repair depends on the pulmonary valve annulus size; the z score of the pulmonary annulus is the most commonly used predictor. However, definitive results are not obtained with z scores as different z score data sets are used for different parameters. Purpose: This study aimed to identify the echocardiographic and other key factors that warranted a change in the surgical method during TOF surgery. Methods: Sixty-two patients were enrolled and divided into a pulmonary valve (PV) preservation group and a TAP group. Their medical records were reviewed. Results: The z score for PV annulus (PVA), ratio of the PVA to aortic annulus size, and ratio of PVA to descending aorta (DAO) size were significantly different between the PV preservation and TAP groups (-1.72±1.52 vs. -3.07±1.94, P=0.004; 0.62±0.12 vs. 0.50±0.14, P=0.002; and 1.32±0.32 vs. 1.07±0.36, P=0.008, respectively). For TAP repair, the PVA z score had a sensitivity of 65.4% and specificity of 73.1%, ratio of PVA to aortic annulus size had a sensitivity of 73.1% and specificity of 65.4%, and ratio of PVA to DAO size had a sensitivity of 69.2% and specificity of 57.7%. The TAP group showed more monocuspid PVs (P=0.011), while the PV preservation group showed more tricuspid PVs (P=0.027). Commissurotomy was more frequently performed in the PV preservation group than in the TAP group (P=0.001). Of patients with commissurotomy, 58% showed a PV z score<-2. Conclusion: Although various echocardiographic parameters may serve as predictors for determining surgical methods for TOF patients, the PV morphology and tissue characteristics should also be considered.

• Journal of Chest Surgery
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• 제36권12호
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• pp.921-927
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• 2003

동맥전환술은 대혈관전위증의 가장 효과적인 수술 방법이 되어왔다. 그러나 동맥전환술 후 신생대동맥근부가 과도하게 확장되는 현상이 보고되었으며, 이에 따른 신생대동맥판막의 기능과 대동맥의 성장에 미치는 영향에 대해서는 잘 알려져 있지 않다. 본 연구에서는 신생대동맥판막과 대동맥의 수술 후 크기의 변화와 신생대동맥판막의 기능 및 기능에 영향을 미치는 요인을 조사하였다. 대상 및 방법: 대동맥전환술을 받고 추적관찰기간 중 심도자술을 시행 받은 48명의 환자들이 연구 대상이 되었으며, 동맥전환술은 나이 중앙값 생후 18일(1∼211일)에 시행받았다. 수술 전 심도자술은 26명의 환자에서 시행되었고, 수술 후 15.8$\pm$9.6개월에 모든 환자에서 심도자술을 시행하였다. 수술 후의 하행대동맥에 대한 신생대동맥륜, 대동맥근부과 대동맥문합부위의 직경 비율을 수술 전의 폐동맥륜, 근위부 및 동관경계부위의 크기와 비교하였다. 수술 전과 수술 시의 변수에 대한 신생대동맥판막폐쇄부전의 위험인자를 분석하였다. 결과: 추적관찰 중 2명의 환자에서 중등도 이상의(grade$\geq$II/IV) 대동맥판막폐쇄부전이 있었으며 이 중 1명은 대동맥판막치환술이 필요하였다. 1명의 환자에서 대동맥문합부 협착으로 재수술이 필요하였다. 수술 후 neoaortic annulus/DA 비는 1.33$\pm$0.28에서 1.52$\pm$0.33로 증가하였고(p=0.01), neoaortic root/DA 비도 2.02$\pm$0.40에서 2.56$\pm$0.38로 증가하였다(p<0.0001). 그러나 aortic anastomosis/DA 비는 통계적으로 유의한 차이는 없었다(p=0.06). 신생대동맥판폐쇄부전의 발생과 neoaortic annulus/DA 비, neoaortic root/DA 비율에는 통계적으로 유의한 상관관계는 없었다. 신생아기 이후의 교정(나이>30일)(p=0.02), 수술 전 폐동맥판막협착(p=0.01)과 이엽성폐동맥판막(p=0.03)이 단일변수 분석에서 대동맥판막폐쇄부전의 위험인자이었다. 결론: 동맥전환술 후 대동맥문합부는 하행대동맥의 성장에 비례하는 정상 성장을 보이나 신생대동맥판막륜과 대동맥근부는 이상 확장을 보였다. 신생대동맥판막륜과 대동맥근부의 크기는 대동맥폐쇄부전과 직접적으로 연관되어 있지 않았으며, 임상적으로 의미 있는 대동맥판막폐쇄부전은 동맥전환술 후 드물게 발생했다. 신생아기 이후의 동맥전환술, 수술 전 폐동맥협착, 이엽성 폐동맥판막이 신생대동맥판막 폐쇄부전의 위험인자였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.773-774
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• 2005

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.121.2-121
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• 1999