• Bulletin of the Korean Chemical Society
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• 제24권4호
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• pp.499-503
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• 2003

Encapsulation of L-ascorbic acid (vitamin C) within a bio-compatible layered inorganic material was achieved by coprecipitation reaction, in which the layered inorganic lattice and its intercalate of vitamin C are simultaneously formed. The nano-meter sized powders of vitamin C intercalate thus prepared was again encapsulated with silica nano-sol to form a nanoporous shell structure. This ternary nanohybrid of vitamin Clayered inorganic core-$SiO_2$ shell exhibited an enhanced storage stability and a sustained releasing of vitamin C. Furthermore, the nano-encapsulation of vitamin C with inorganic mineral was very helpful in delivering vitamin C molecules into skin through stratum corneum, facilitating transdermal penetration of vitamin C in topical application.

• Nuclear Engineering and Technology
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• 제38권2호
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• pp.119-128
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• 2006

We start to develop a predictable technology for thermal-hydraulic performance of the RMWR core using an advanced numerical simulation technology. As a part of this technology development, we are developing the advanced interface tracking method to improve the conservation of volume of fluid. The present paper describes a part of the development of the twophase flow simulation code TPFIT with the advanced interface tracking method. The numerical results applied to large-scale water-vapor two-phase flow in tight lattice rod bundles are shown and compared with experimental results. In the results of numerical simulation, a tendency of the predicted void fraction distribution in horizontal plane agreed with the measured values obtained by the advanced neutron radiography technique including the bridge formation of the liquid at the position of adjacent fuel rods where an interval is the narrowest.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2001년도 봄 학술발표회 논문집
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• pp.563-570
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• 2001

In this study, the charactersistics of horizontal drains used to stabilize the dredged fill are investigated experimentally by doing tensile strength test, discharge capacity test, and filter clogging test. The types of the drains selected for the study are filament type (Tyre-E), embossed type(Type-P) and heat bonded cubic type with the thickness 10mm(Type-010) and 5mm(Type-05). The results of tensile strength and discharge capacity test show that the performance of drain Type-O10 was better than the other drains. This is caused by the fact that the lattice shape core of drain Type-O10 has strong rigidity and minimizes the loss of the sectional area of discharge with increased confining pressure. Analyzing the compatibility of filters by the results of the strength characteristics test and clogging test, the filter of filament type drain produced with polyester clothed polyamide performed well.

• 한국항공운항학회지
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• 제14권2호
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• pp.17-26
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• 2006

The flutter characteristics of all movable tail wing with honeycomb sandwich structure have been studied in this study. The present wing model has a airfoil cross section and the linear variation of spanwise thickness. Structural vibration analysis is performed based on the finite element method using sandwich and beam elements. Unsteady aerodynamic technique used on the doublet lattice method has been effectively used to conduct the frequency-domain flutter analyses. The parametric flutter studies have been performed for various structural design parameters. Computational results on flutter stability due to the variation of structural parameters are presented and its related characteristics are investigated through the comparison of results.

• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 2003년도 춘계학술대회논문집
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• pp.101-105
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• 2003

본 논문은 고리 1호기 원자력발전소를 기준발전소로 하여 개발된 PRE-MARK 소개 및 PRE-MARK을 기반으로 개발된 노심모델의 결과를 제시하고자 하는 것을 주된 목적으로 하고 있다. 노심 모델개발에는 REMARK 모델 프로그램을 기반으로 개발된 PRE-MARK를 이용하였으며, PRE-MARK의 주요 특징으로는 노심모델 입력자료를 노심설계코드 및 Lattice 코드로부터 자동으로 생성하며여 GUI 기반으로 변경된 REMARK으로 입력하여 노심모델을 구동함과 동시에 실시간으로 중요 변수의 현재 값들을 그래프로 도시해줌으로 조율 (Tuning) 상수를 용이하게 결정할 수 있도록 하는 것이다. 또한 BOL 및 EOL에서 HFP 평형 Xenon조건에서의 제어봉 위치에 따른 제어봉가(Rod worth)를 고리 1호기 20주기 NDR (Nuclear Design Report)과 비교하고, 원자로정지 이후 BOL, MOL 및 EOL에서의 시간에 따른 Xenon의 반응도 영향을 비교함으로 개발된 모델의 건전성을 입증하였다.

• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 2000년도 추계학술대회 논문집
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• pp.78-83
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• 2000

본 논문은 영광 1호기 원자력발전소를 기준발전소로 하여 개발된 PRE-MARK 소개 및 PRE-MARK을 기반으로 개발된 노심모델의 결과를 제시하고자 하는 것을 주된 목적으로 하고 있다. 노심 모델개발에는 REMARK 모델 프로그램을 기반으로 개발된 PRE-MARK를 이용하였으며, PRE-MARK의 주요 특징으로는 노심모델 입력자료를 노심설계코드 및 Lattice코드로부터 자동으로 생성하며 GUI 기반으로 변경된 REMARK으로 입력하여 노심모델을 구동함과 동시에 실시간으로 중요 변수의 현재 값들을 그래프로 도시해줌으로 조율 (Tuning) 상수를 용이하게 결정할 수 있도록 하는 것이다 또한 BOL 및 EOL에서 HFP 평형 Xenon 조건에서의 제어봉 위치에 따른 제어봉가(Rod worth)를 영광 1호기 12주기 NDR(Nuclear Design Report)과 비교하고, 원자로정지 이후 BOL, MOL 및 EOL에서의 시간에 따른 Xenon의 반응도 영향을 비교함으로 개발된 모델의 건전성을 입증하였다.

• 한국자기학회지
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• 제5권5호
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• pp.610-613
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• 1995

The effect of processing parameters such as milling, additives and sintering atmoshpere on the magnetic properties of Mn-Zn ferrite was investigated. The experiment was followed by general ceramic fabrication process and added additives were $CaCO_{3}$, $SiO_{2}$, $V_{2}O_{5}$, $ZrO_{2}$, and $Nb_{2}O_{5}$. The effects of additives could be divided into three categories which were formation ofliquid phase, substitution in lattice and inducing stress. Core loss smong the magnetic properties was dependent mainly on the additives and also correlated with processing parameters. As a result, an optimum condition of preparing process for a high quality Mn-Zn ferrite was suggested by controlling the correlation of each processing parameters.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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• pp.185-190
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• 1996

RFSP is a computer program to do fuel management calculations for CANDU reactors. Its main function is to calculate neutron flux and power distributions using two-energy-group, three dimensional neutron diffusion theory. However, up to now the treatment has not been true two-group but actually "one-and-half groups". In other words, the previous (1.5-group) version of RFSP lumps the fast fission term into the thermal fission term. This is based on the POWDERPUFS-V Westcott convention. Also, there is no up-scattering term or bundle power over cell flux (H1 factor) for the fast group. While POWDERPUFS-V provides only 1.5 group properties, true two-group cross sections for the design and analysis of CAUDU reactors can be obtained from WIMS-AECL. To treat the full two-group properties, the previous RFSP version was modified by adding the fast fission, up-scatter terms, and H1 factor. This two-group version of RFSP is a convenient tool to accept lattice properties from any advanced lattice code (e.g. WIMS-AECL DRAGON, HELIOS...) and to apply to advanced fuel cycles. In this study, the modification to implement the true two-group treatment was performed only in the subroutines of the ＊SIMULATE module of RFSP. This module is the appropriate one to modify first, since it is used for the tracking of reactor operating histories. The modified two-group RFSP was evaluated with true two-group cross sections from WIMS-AECL. Some tests were performed to verify the modified two-group RFSP and to evaluate the effects of fast fission and up-scatter for three core conditions and four cases corresponding to each condition. The comparisons show that the two-group results are quite reasonable and serve as a verification of the modifications made to RFSP. To assess the long-term impact of the full 2-group treatment, it is necessary to simulate a long period (several months) of reactor history. It will also be necessary to implement the full two-group treatment of reactivity devices and assess the reactivity-device worths.ce worths.

• 한국초등수학교육학회지
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• 제14권2호
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• pp.287-314
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• 2010

알고리즘을 지도하는 전통적인 방법은 우선 '표준 알고리즘'을 완성된 형태로 제시하고 이어서 간단한 사례를 통하여 이해한 다음, 보다 일반적인 문제에 적용함으로써 표준 알고리즘을 연습하는 형태이다. 그러나 이 방법은 표준 알고리즘에 지나치게 집중되어 있다는 문제점과 함께, 학생 스스로 문제에 적합한 알고리즘을 선택하거나 알고리즘 자체를 개발하는 경험을 제공하지 못한다는 제한점을 갖고 있다. 이 논문에서는 자연수 곱셈 알고리즘의 다양성을 활용하여 학생 스스로 알고리즘을 개발하고 발명할 수 있도록 지도하는 방안을 상세하게 구안하였고, 그에 따른 교수실험을 통하여 초등학교 3학년 학생의 곱셈 알고리즘에 대한 이해 과정을 분석하였다. 그 결과는 첫째, 실험적인 지도안으로 학습한 실험반은 자리값의 원리와 분배법칙의 이해에 있어서 비교반보다 높은 성취를 보였으나, 계산 능력에 있어서는 그렇지 못했다. 둘째, 비교반은 물론 실험반에서도 표준 알고리즘의 선호도가 가장 높았으며, 실험반에서는 표준 알고리즘 다음으로 격자곱셈의 선호도가 높은 것으로 나타났다. 격자 곱셈을 교육 소재로 활용하는 것을 적극 고려할 필요가 있다. 셋째, 비례표는 그것이 가지는 이론적인 장점에도 불구하고 우리나라 초등학교 3학년 학생이 배우기에는 다소 무리가 따르는 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1120-1130
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• 2020

The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices. To analyze these experiments with accuracy an elaborate calculation scheme using the Monte Carlo method implemented in the MCNP6.1 code and the ENDF/B-VII.1 cross section library has been developed. We have used the ENDF/B-VII.1 data provided with the MCNP6.1.1 version in ACE format and the Makxsf utility to handle the data in the specific temperatures not available in the MCNP6.1.1 original library. The main purpose of this analysis is the qualification of the ENDF/B-VII.1 nuclear data for the prediction of the Reactivity Temperature Coefficient while ensuring the ability of the MCNP6.1 system to model such a complex experiment as CREOLE. We have analyzed the case of UO₂ lattice with 1166 ppm of boron in ordinary water moderator in specified temperatures. A detailed comparison of the calculated effective multiplication factors with the reference ones [1] in room temperature presented in this work shows a good agreement demonstrating the validation of our 3D calculation model. The discrepancies between calculations and the differential measurements of the Reactivity Temperature Coefficient for the analyzed configuration are relatively small: the maximum discrepancy doesn't exceed 1,1 pcm/℃. In addition to the analysis of direct differential measurements of the reactivity temperature coefficient performed in the poisoned UO₂ lattice configuration, we have also analyzed integral measurements in UO₂ clean lattice configuration using equivalency of the integral temperature reactivity worth with the driver core fuel reactivity worth and soluble boron reactivity worth. In this case both of the ENDF/B-VII.1 and JENDL.4 libraries were used in our analysis and the obtained results are very similar.