고령자의 상실감이 주관적 안녕감에 미치는 영향

윤훈,이순철,오주석 한국문화및사회문제심리학회 2007 한국심리학회지: 문화 및 사회문제 Vol.13 No.2

The purpose of this study is to find how the factors of “Grief of loss” affect on the subjective well-being of elderly(‘the satisfaction with life’, ‘the positive affect’, ‘the negative affect). One hundred of subjects, over age 65, participated in the survey and we could find that the “Grief of loss” was composed of four sub-factors(‘economical loss’, ‘loss from being parted by death’, ‘loss of physical functions’, ‘loss of relations’). These four sub-factors of “Grief of loss” showed negative correlations with the scores of the satisfaction with life. However, three other sub-factors except ‘loss from being parted by death’ showed negative correlations with the scores of ‘the positive affect’. On the other hand, other three sub-factors except ‘economical loss’ showed positive correlations with the scores of ‘the negative affect’. Especially, the ‘economical loss’ was affecting on ‘the negative affect’ and ‘the positive affect’ significantly. Also, 'loss of relations' was affecting on both ‘the negative affect’ and ‘the satisfaction with life’'. Two out of the four sub-factors, ‘economical loss’ and ‘loss from being parted by death’, showed no significant effects on the subjective well-being. This results insists us that the emotional supports, especially from their offspring, are truly important for elderly to overcome their Grief of loss('loss of physical functions', ‘loss of relations’) 본 연구는 고령자들이 경험하는 상실감이 주관적 안녕감에 어떠한 영향을 미치는 살펴보고자 하였다. 이를 위해서 만 65세 이상 고령자 총 100명을 대상으로 자료를 수집하여 분석한 결과, 고령자 상실감 요인인 ‘건강 상실’, ‘관계의 상실’, ‘경제적 상실’, ‘사별 상실’은 ‘생활 만족도’와는 부적인 상관을 나타냈으며, ‘정적 정서’와는 ‘사별 상실’을 제외한 세 요인들이 부적인 상관을 나타냈다. 그리고 ‘부정 정서’와는 ‘경제적 상실’을 제외한 나머지 세 요인들과는 정적인 상관을 가지고 있었다. 그리고 경로분석을 통해 상실감 하위요인들이 주관적 안녕감에 이르는 과정을 살펴보았다. 그 결과, ‘건강 상실’요인은 주관적 안녕감의 ‘정적 정서’와 ‘부적 정서’에 영향을 미치는 요인으로 나타났다. 그리고 ‘관계의 상실’요인은 ‘생활 만족도’와 ‘정적 정서’에 유의한 영향을 미치는 것으로 나타났다. 한편 ‘경제적 상실’과 ‘사별 상실’요인은 주관적 안녕감에 미치는 유의한 영향력이 없는 것으로 나타났다. 이것은 고령자들의 건강문제와 가족관계에서는 정서적 지원이 중요하고, 특히. 고령자의 건강문제와 가족관계에서 가족의 지원이 중요함을 시사한다.

租稅不服制度에 관한 考察

윤훈 서울市立大學校 經商大學 稅務學科 2000 稅務學論集 Vol.13 No.1

Development of Wall-Thinning Evaluation Procedure for Nuclear Power Plant Piping — Part 1: Quantifi cation of Thickness Measurement Deviation

윤훈,문승재,오영진 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.3

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

日本語CALLにおける?習支援者の評?に?する?究

尹?勛 일본어문학회 2006 일본어문학회 국제학술대회 Vol.- No.-

Multi-Level Capacitive Memory Effect in Metal/Oxide/Floating-Schottky Junction

최가현,윤훈한,박기복,김준형,정성철,정윤욱 한국물리학회 2019 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.74 No.10

We experimentally demonstrate that metal/oxide/floating-Schottky junction has multiple effective capacitances depending on the amount of electrons stored in the floating metal electrode. The oxide thin film covering the Schottky junction is used to trap electrons in the floating metal. The electron flow into and out of the floating metal is controlled by applying voltage pulses of opposite polarities onto the semiconductor substrate. With the amount of excess charges in the floating metal, the depletion capacitance of Schottky junction varies synchronously, which dominantly affects the effective capacitance of the whole junction. Interestingly, the capacitance of metal/oxide/floating-Schottky junction measured as a function of applied voltage pulse shows a hysteretic behavior, which supports its capacitive memory effect. It is expected that our metal/oxide/floating-Schottky junction can work as a memcapacitor capable of recording multiple switchable capacitance values and it can be readily fabricated with the current Si CMOS technology.

원전 배관의 두께 측정 데이터에 대한 신뢰도 분석 방법 및 적용

윤훈 ( Hun Yun ),황경모 ( Kyeong Mo Hwang ),이효승 ( Hyo Seoung Lee ),문승재 ( Seung Jae Moon ) 한국부식방식학회(구 한국부식학회) 2015 Corrosion Science and Technology Vol.14 No.1

Pipe wall-thinning by flow-accelerated corrosion and various types of erosion is significant damage in secondary system piping of nuclear power plants(NPPs). All NPPs in Korea have management programs to ensure pipe integrity from degradation mechanisms. Ultrasonic test(UT) is widely used for pipe wall thickness measurement. Numerous UT measurements have been performed during scheduled outages. Wall-thinning rates are determined conservatively according to several evaluation methods developed by Electric Power Research Institute(EPRI). The issue of reliability caused by measurement error should be considered in the process of evaluation. The reliability analysis method was developed for single and multiple measurement data in the previous researches. This paper describes the application results of reliability analysis method to real measurement data during scheduled outage and proved its benefits.

예측모델 및 실험을 통한 액적충돌침식 손상 평가

윤훈(Hun Yun),황경모(Kyeong Mo Hwang) 대한기계학회 2011 大韓機械學會論文集B Vol.35 No.10

유동가속부식(FAC)은 가장 잘 알려진 탄소강 배관 손상 메커니즘으로 현재 국내 전 원전에서는 유동가속부식으로 인한 감육현상을 관리할 수 있는 체계적인 방안이 수립되어 있다. 그러나, 발전소 배관은 다양한 침식손상 메커니즘에 의해 여전히 손상을 받고 있다. 대표적인 침식 메커니즘은 캐비테이션, 액적충돌침식(LDIE), 플래싱, 고체입자침식(SPE)이다. 본 논문에서 기술하는 액적충돌침식 은 손상 예측이 어렵고, 관리를 위한 체계적인 방안도 수립되어 있지 않다. 본 논문에서는 실제 발전소 현장에서 발생한 사례를 바탕으로 기존에 개발된 예측 모델과 실험을 통해 얻어진 상관식을 비교하여 액적충돌침식으로 인한 손상을 평가할 수 있는 방법을 제시하였다. Flow-accelerated corrosion (FAC) is a well-known phenomenon that may occur in piping and components. Most nuclear power plants have carbon-steel-pipe wall-thinning management programs in place to control FAC. However, various other erosion mechanisms may also occur in carbon-steel piping. The most common forms of erosion encountered (cavitation, flashing, Liquid Droplet Impingement Erosion (LDIE), and Solid Particle Erosion (SPE)), have caused wall thinning, leaks, and ruptures, and have resulted in unplanned shutdowns in utilities. In particular, the damage caused by LDIE is difficult to predict, and there has been no effort to protect piping from erosive damage. This paper presents an evaluation method for LDIE. It also includes the calculation results from prediction models, a review of the experimental results, and a comparison between the UT data in the damaged components and the results of the calculations and experiments.

원전 2차계통의 출력증강 운전에 따른 배관감육 영향 분석

윤훈 ( Hun Yun ),황경모 ( Kyeong Mo Hwang ),이효승 ( Hyo Seoung Lee ),문승재 ( Seung-jae Moon ) 한국부식방식학회(구 한국부식학회) 2016 Corrosion Science and Technology Vol.15 No.3

Piping and equipment are degraded by flow-accelerated corrosion (FAC) in nuclear power plants. FAC causes numerous problems and nuclear utilities maintain programs to control FAC. The key parameters influencing FAC are hydrodynamic conditions, water chemistry, and effect of materials. Recently, a nuclear utility has planned slight power uprates in Korea. Operating conditions need to be changed in the secondary system according to power uprates. This study analyzed the effect of wall-thinning caused by power uprates. The change of operation data in the secondary cycle is reviewed, and wall-thinning rates are analyzed in the main lines. As a result, two phase (mixture of water and steam) lines have a greater impact than a water line under power uprate conditions. Also, the quality of steam is the most important factor for FAC in two phase lines.

〈기술논문〉 원전 탄소강 배관의 국부감육 현상과 난류 속도성분의 상관관계 확인

윤훈(Hun Yun),황경모(Kyeong Mo Hwang),진태은(Tae Eun Jin),김경훈(Kyung Hoon Kim) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.5

A study to identify the relation between turbulence coefficient and local wall thinning inside carbon steel piping was performed. Experiments and numerical analyses for the several types of downscaled piping components took place and the results were compared with each other. Based on the results indicating that flow behaviors inside piping components can be sufficiently simulated by numerical analysis, numerical analysis for the models magnified to the actual size of plants was carried out. To identifythe relation between turbulence coefficients and local wear rate, numerical analysis was performed for 17 components of 9 types included in feedwater system. Turbulence coefficients resulting from numerical analysis were compared with local wear rates based on the measured data. From the comparison of the results, the vertical flow velocity component (Vr) flowing again to the wall after having separated due to geometrical configurations or colliding with wall directly at an angle of some degrees was analogous to the configuration of local wall thinning. From the least squares fitting result, it was derived that the average relationship between the Vr and local wear rate is in proportion to 0.55 time of the Vr adding 0.1 with the standard deviation of 0.65.

예측모델 및 실험을 통한 액적충돌침식 손상 평가에 대한 연구

윤훈(Hun Yun),황경모(Kyeong Mo Hwang) 대한기계학회 2011 대한기계학회 춘추학술대회 Vol.2011 No.4

유동가속부식(FAC)은 가장 잘 알려진 탄소강 배관 손상 메커니즘으로 현재 국내 전 원전에서는 유동가속부식으로 인한 감육현상을 관리할 수 있는 체계적인 방안이 수립되어 있다. 그러나, 발전소 배관은 다양한 침식손상 메커니즘에 의해 여전히 손상을 받고 있다. 대표적인 침식 메커니즘은 캐비테이션, 액적충돌침식(LDIE), 플래싱, 고체입자침식(SPE)이다. 본 논문에서 기술하는 액적충돌침식은 손상 예측이 어렵고, 관리를 위한 체계적인 방안도 수립되어 있지 않다. 본 논문에서는 실제 발전소 현장에서 발생한 사례를 바탕으로 기존에 개발된 예측 모델과 실험을 통해 얻어진 상관식을 비교하여 액적충돌침식으로 인한 손상을 평가할 수 있는 방법을 제시하였다. FAC is a well-known phenomenon that may occur in piping and components. Most nuclear power plants have carbon steel pipe wall thinning management programs in place to control flow-accelerated corrosion (FAC). However, various erosion mechanisms may also occur in carbon steel piping. The most common forms of erosion encountered, cavitation, flashing, LDIE(Liquid Droplet Impingement Erosion), and SPE(Solid Particle Erosion), have caused wall thinning, leaks, and ruptures and results in unplanned shutdowns in utilities. Especially LDIE is difficult to predict damage and there has not been an effort to protect piping from erosive damage. This paper presents the evaluation method for the LDIE. This paper also includes the calculation result using prediction models, the review of the experiment result, and the comparison between the UT data in the damaged component and the results of calculation and experiment.