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TARGIS & VECTRIS SYSTEM을 이용한 심미적 수복
최현식,황정원,신상완,서규원,Choi, H.S.,Hwang, J.W.,Shin, S.W.,Suh, K.W. 대한심미치과학회 1998 Journal of the Korean Academy of Esthetic Dentistr Vol.7 No.1
The improvement of esthetic dentistry has been accelerated from the development of composite resin and dentin-enamel adhesive since 1980's. The indirect composite resin restorations have more accurate proximal contact point and occlusal form than direct restoration. And the side effect of resin shrinkage is minimal because the amount of composite used in oral cavity is limited in cement space. As a results, marginal leakage, hypersensitivity, secondary caries, and discoloration are significantly diminished. The first generation laboratory composite resin used in indirect resin restoration had been widespread in 1980's and the second generation laboratory composite resins were developed in 1990's. The second generation laboratory composite resins are called Ceramic Polymer. The physical properties of Ceramic Polymer are improved because of high content of inorganic filler, and the esthetics and biocompatibility are better than that of the first generation resin. So the application range using composite resin have been broadened. The purpose of this paper is to introduce Targis & Vectris system that is classified to second generation laboratory composite and to report several cases in which the system was utilized for restoration.
정원대,황미정 한국산업안전학회 1997 한국안전학회지 Vol.12 No.4
Probabilistic Safety Assessment(PSA) is an engineering analysis of the possible contributors to the risk from a nuclear power plant. It consist of three phases named as Level 1, 2 and 3. Level 1 PSA mainly focused in this paper is the phase of system analysis which includes the development of accident scenarios and the frequency estimation of each scenario. It covers also the system reliability analysis, component data analysis, and human reliability analysis. PSA have become a standard tool in safety evaluation of nuclear power plants. The main benefit of PSA is to provide insights into plant design, performance and environmental impacts, including the identification of dominant risk contributors and the comparison of options for reducing risk.
확률론적 안전성평가를 위한 일반 기기 신뢰도 데이타 베이스 구축 절차와 적용
김길유,김태운,정원대,황미정,임태진 한국산업안전학회 1997 한국안전학회지 Vol.12 No.4
건설중이거나 기기 이력이 부족한 원자력 발전소에 대한 확률론적 안전성평가에 사용되는 일반 기기 신뢰도 데이타를 기 개발된 일반 데이타 및 발전소 데이타를 취합하여 구한다. 이를 위해 본 논문에서 사용한 계산 Code는 모수적 선험적 베이지안 방떱에 근거하여 3단계 베이지안 방법으로 한국원자력연구소에서 개발한 MPRDP Code이다. 일반 자교원에서 주로 자료를 취합하였으므로 각 문헌들 사이에 존재할 수 있는 종속성을 고려하여 Code에서 처리하였다. 본 논문에서는 결과로 얻어진 기기 신뢰도 자료표의 일부분을 보여준다. This paper presents the development procedure and application of the generic component reliability data base considering the dependency among dependent generic compendia in NPPs (Nuclear Power Plants) PSA (Probabilistic Safety Assessment) under construction or without operating history. We use MPRDP (Multi-Purpose Reliability Data Processor) code developed in KAERI (Korea Atomic Energy Research Institute) based on a PEB (Parametric Empirical Bayesian) procedure to estimate the reliability. The employed model in this study accounts for the relative credibility as well as the dependency among generic estimates. Numerical examples and the part of summarized reliability data table are provided as the application.