• 한국정보통신학회:학술대회논문집
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• 한국해양정보통신학회 2006년도 춘계종합학술대회
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• pp.668-671
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• 2006

초고속 인터넷과 웹의 급속한 성장으로 인해 우리가 살고 있는 사회에 많은 영향을 미쳤고 교육분야에도 영향을 미쳤다. 초고속 인터넷의 급속한 성장은 정보화 사회에 대응을 할 수 있는 교육으로 이끌고자 교육개혁을 추진하고 있다. 정보화 사회에 대처할 수 있는 능력함양을 위해 정보화교육을 강조하기 위해 7차 교육과정에 포함이 되어 있으며 국가 차원에서 교육정보화를 위해 많은 사업을 하고 있다. 그러나 초등학교에서는 정보화 교육에 대한 정확한 명시와 이에 대한 교육내용이 제시되고 있지 않아 재량활동의 일부분으로 컴퓨터 교육이 이루어지고 있어 마땅한 정보화 교육관련 교재 및 초등학생들의 수준별 교육이 이루어지지 않아 제대로 된 정보화 교육이 이루어지지 않고 있는 실정이다. 본 연구는 홈페이지 기반의 교수-학습을 이용하여 학습자가 자기 주도적으로 스스로 학습하고 학습에 대한 결과를 평가 할 수 있는 기회를 제공함으로서 주도적으로 학습을 할 수 있게 하고, 수준별 학습을 할 수 있는 패러다임을 제공하고자 한다.

• Restorative Dentistry and Endodontics
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• 제25권1호
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• pp.123-132
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• 2000

To overcome problems of conventional glass ionomers, resin components have been added to glass ionomers. On a continuum between glass ionomers and composites are a variety of blends, employing different proportions of acid-base and free radical reactions to bring about cure. Popular groups defined between the ends are resin-modified glass-ionomers(RMGIs), polyacid-modified composite resins(Compomers) and ionomer modified resins. These groups show different clinical properties, and in selecting these materials for a restoration, one should sufficiently understand these different setting properties. In this study, some difference in the setting characteristics of different groups of hybrid ionomers were examined. Two RMGIs (Fuji2 LC,GC / Vitremer, 3M), three Compomers (Dyract AP, Dentsply / F2000, 3M / Elan, Kerr) were involved in this study. The identification of the setting characteristics of different groups was achieved by a two-stage study. First, thermal analysis was performed by a differential scanning calorimeter, and then the hardness of each group at different depth and time were measured by a micro-hardness tester. Thermal analysis was performed to identify the inorganic filler content and to record the heat change during setting process. The setting process was progressed for each material by chemical set mode and light-cured mode. In the hardness test, samples of materials were prepared with a 6mm-diameter metal ring, and the hardness was measured at the top, and 1mm, 2.5mm, 4mm below at just after a 40 second-cure, and after 10 minutes, 24 hours, and 7 days. Statistical analysis was performed by Mann-Whitney rank sum test to assess significant differences between set modes and types of materials, and by ANOVA and T-test to evaluate the statistical meanings of data at different times and depths of each materials. Followings are findings and conclusions derived from this study. Thermal analysis; 1. Compomers show no evidence of chemical setting while RMGIs exhibit heat output during the process of chemical setting. 2. Heat of cure of RMGIs exceed Compomers. 3. The net heat output of RMGIs through light-cured mode is higher than through chemically set mode. Hardness test; 1. Initial hardness of RMGIs immediately after light cure is relatively low, but the hardness increases as time goes by. On the contrary, Comomers do not show evident increase of the hardness following time. 2. Compomers show a marked decrease of setting degree as the depth of the material increases. In RMGIs, the setting degree at different depths does not significantly differ.

• 대한지리학회지
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• 제39권2호
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• pp.269-282
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• 2004

태안반도 신두리 일대에 분포하는 전사구 퇴적물에 대한 OSL 연대측정결과, 조사 지점에서의 사구사 퇴적은 대략 500-600년 전에 시작되었다. 이후 사구층 하부는 안정상태를 유지했으나, 상부(지표에서 1cm)의 연대가 약 30년전인 것으로 보아 1970년대 이후 재퇴적되었을 것으로 추정된다. 한편, 사구 표면으로부터 3.5m와 2m 깊이에서 채취한 두 개의 시료는 50-70년 정도의 연대차이가 있다. 이에 의하면 사구사의 순 퇴적율은 연간 약 2.5cm로 추정되는데, 이는 해안사구로서는 비교적 느린 것이다. 본 조사에서 연대를 추정한 사구사 퇴적층은 1개 시점에 불과하지만, 이를 토대로 볼 때, 지난 1,000년간 상당한 양의 사구사가 퇴적되었거나 재이동되었음을 알 수 있다. 이러한 사실은 사구가 홀로세(Holocene) 동안에도 매우 역동적으로 움직이고 있음을 시사한다. SEM 및 입도분석을 토대로 볼 때, 사구사는 수중환경에서 쌓인 이후 바람에 의해 재운반되어 퇴적된 모래 입자의 특성과 잘 부합된다.

• Nuclear Engineering and Technology
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• 제39권1호
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• pp.31-42
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• 2007

Energy supply is increasingly showing up as a major issue for electricity supply, transportation, settlement, and process heat industrial supply including hydrogen production. Nuclear power is part of the solution. For electricity supply, as exemplified in Finland and France, the EPR brings an immediate answer; HTR could bring another solution in some specific cases. For other supply, mostly heat, the HTR brings a solution inaccessible to conventional nuclear power plants for very high or even high temperature. As fossil fuels costs increase and efforts to avoid generation of Greenhouse gases are implemented, a market for nuclear generated process heat will be developed. Following active developments in the 80's, HTR have been put on the back burner up to 5 years ago. Light water reactors are widely dominating the nuclear production field today. However, interest in the HTR technology was renewed in the past few years. Several commercial projects are actively promoted, most of them aiming at electricity production. ANTARES is today AREVA's response to the cogeneration market. It distinguishes itself from other concepts with its indirect cycle design powering a combined cycle power plant. Several reasons support this design choice, one of the most important of which is the design flexibility to adapt readily to combined heat and power applications. From the start, AREVA made the choice of such flexibility with the belief that the HTR market is not so much in competition with LWR in the sole electricity market but in the specific added value market of cogeneration and process heat. In view of the volatility of the costs of fossil fuels, AREVA's choice brings to the large industrial heat applications the fuel cost predictability of nuclear fuel with the efficiency of a high temperature heat source tree of Greenhouse gases emissions. The ANTARES module produces 600 MWth which can be split into the required process heat, the remaining power drives an adapted prorated electric plant. Depending on the process heat temperature and power needs, up to 80% of the nuclear heat is converted into useful power. An important feature of the design is the standardization of the heat source, as independent as possible of the process heat application. This should expedite licensing. The essential conditions for success include: ${\bullet}$ Timely adapted licensing process and regulations, codes and standards for such application and design ${\bullet}$ An industry oriented R&D program to meet the technological challenges making the best use of the international collaboration. Gen IV could be the vector ${\bullet}$ Identification of an end user(or a consortium of) willing to fund a FOAK

• Nuclear Engineering and Technology
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• 제50권2호
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• pp.268-279
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• 2018

The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NP within the PLEIADES software environment models the behavior of fuel rods during irradiation in commercial pressurized water reactors (PWRs), power ramps in experimental reactors, or accidental conditions such as loss of coolant accidents or reactivity-initiated accidents (RIAs). As regards the latter case of transient in particular, ALCYONE is intended to predictively simulate the response of a fuel rod by taking account of mechanisms in a way that models the physics as closely as possible, encompassing all possible stages of the transient as well as various fuel/cladding material types and irradiation conditions of interest. On the way to complying with these objectives, ALCYONE development and validation shall include tests on $PWR-UO_2$ fuel rods with advanced claddings such as M5(R) under "low pressure-low temperature" or "high pressure-high temperature" water coolant conditions. This article first presents ALCYONE V1.4 RIA-related features and modeling. It especially focuses on recent developments dedicated on the one hand to nonsteady water heat and mass transport and on the other hand to the modeling of grain boundary cracking-induced fission gas release and swelling. This article then compares some simulations of RIA transients performed on $UO_2$-M5(R) fuel rods in flowing sodium or stagnant water coolant conditions to the relevant experimental results gained from tests performed in either the French CABRI or the Japanese NSRR nuclear transient reactor facilities. It shows in particular to what extent ALCYONE-starting from base irradiation conditions it itself computes-is currently able to handle both the first stage of the transient, namely the pellet-cladding mechanical interaction phase, and the second stage of the transient, should a boiling crisis occur. Areas of improvement are finally discussed with a view to simulating and analyzing further tests to be performed under prototypical PWR conditions within the CABRI International Program. M5(R) is a trademark or a registered trademark of AREVA NP in the USA or other countries.

• 한국식품위생안전성학회지
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• 제17권3호
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• pp.129-136
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• 2002

본 조사는 계란 유통실태 및 위생상태를 파악하여 품질향상과 위생관리에 도움이 되는 자료를 제공하고자, 2001년 3~4개월에 인천광역시 5개 백화점 식품매장에서 총 57종의 계란을 구입하여 조사하였다. 계란의 포장은 10개 이하의 소량 단위포장 비율이 높았고, 전 품목을 실온에서 보관하였다. 유통기한은 40종(70.2%)이 28일 이상으로 표기하였다. 유통되는 특수란은 31종(54.4%) 이었다. 유통기한과 산란일자는 모든 품목에서 표시되었으며 주로 상표나 난좌에 표기되었다. 내용량에 대한 표시는 38종(66.6%)만이 실시하였다. 난각에 분변이나 털이 있는 경우 27건(9.5%), 난각이 기형이거나 깨진 경우 11건(3.9%), 난 내용물에 혈반이나 육반등의 이물이 있는 경우는 42건(14.7%), 상한 계란은 5건(1.8%)이 유통되었다. Haugh Unit(HU)검사결과 평균은 56.1이었으며, HU 31 미만의 품질저하 계란은 18개(6.3%)이었고,총 57종 중 12종(21.1%)에서 1개 이상의 품질저하 계란이 조사되었다. 난각의 일반세균 오염수준은 <10-8.2$\times$$10^3$cfu/ml로 고르게 분포하였고, 대장균은 8건(4.7%)이 검출되었다. 총 28개의 계란(난황)에서 Salmonella enteritidis는 검출되지 않았고, 계란에 잔류하는 항생물질은 1종에서 테트라사이클린 계열이 검출되었다. 그 동안 위생관리의 사각지대에 있었던 계란에 대한 품질관리와 유통개선을 위한 법적, 제도적 근거가 마련되면, 계란의 표시 및 품질기준 등 사양관리에서부터 유통단계에 이르는 전반적인 안전성 관리방안이 검토되고 보완되어야할 것이다.

• 수산해양기술연구
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• 제43권1호
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• pp.12-27
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• 2007

This fundamental studies on for the productivity improvement and laborsaving of purse seine fishery. Given the difficulty posed from the distortion of net shape caused by the external forces, such as tide, at the time of shooting and pursing, we set the 4 steps of 0, 2, 4 and 6cm/sec in flow velocity in the flume tank for the experiment in order to examine those characteristics. We used two model seines designed on the scale of 1 to 180 based on the power block seine, which is the mackerel purse seine generally used in the near sea of Jeju Island and triplex seine, which is the mackerel purse seine of one boat system fishing expected in the future, for the experiment, and interpreted the characteristics of several motion in water, such as the shape of seine, the change in tension and area during pursing and its the analysis results are as follows. Though the experiment could be conducted up to 6cm/sec of flow velocity that was defined, the experiment could not go on because of the severe distortion in the seine at the flow velocity in excess of 6cm/sec. As for the depth of leadline and reduction rate of side area of seine when the pursing is connected, P seine turned out to be slightly higher than T seine, and the hauling speed and reduction rate of upper area of seine were found similar to each other. The correlation between the hauling time (Ht) and depth of lead line (Dhp, Dht) of P seine and T seine can be expressed by the equation, that is, Dhp=(0.99Pt-7.63)Pt+69.01, Dht=(1.03Pt-7.73)Pt+66.74. The correlation between the hauling time and hauling velocity (Hpp, Hpt) can be expressed by the equation, that is, $Hpp=-0.06Ht^2+0.88Ht+0.78,\;Hpt=-0.05Ht^2+0.81Ht+0.98$ here, Pt is pursing time. And the correlation between the pursing time and the reduction rate of side area (sArp, sArt) can be expressed by the equation, that is, $sArp=-0.48Pt^2+14.79Pt-16.74,\;sArt=-0.45Pt^2+14.56Pt-16.48$. The reduction rate of upper area of seine (tArp, tArt) can be expressed by the equation, that is, $tArp=0.34Pt^2-0.66Pt-0.74,\;tArt=0.34Pt^2-0.27Pt-1.80$. In addition, the correlation between the pursing time and tension of purse line (Tep, Tet) can be expressed by the equation, that is, $Tep=2.79Pt^2+2.26Pt-0.60,\;Tet=2.14Pt^2+8.08Pt-27.50$.

• Current Research on Agriculture and Life Sciences
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• 제4권
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• pp.70-76
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• 1986

평균조차(平均潮差)가 10cm내외(內外)인 포항(浦項) 영일만(迎日灣)으로 유입(流入)하는 형산강(兄山江)의 감조구간(感潮區間)을 채택(採擇)하여 유역내(流域內)의 부조(扶助) 수문기준점(水文基準點)에서 관측(觀測)한 자료(資料)와 하천유량(河川流量) 및 수질측정자료(水質測定資料) 등을 근거(根據)로 밀도유현상(密度流現象)을 분석(分析)한 결과(結果)를 요약(要約)하면 다음과 같다. 1. 영일만(迎日灣)의 조석현상(潮汐現象)은 1일(日)1회조(回潮)이며 대조차(大潮差) 0.104m, 소조차(小潮差) 0.066m, 평균조차(平均潮差) 0.085m로써 해면(海面)의 변동(變動)은 매우 작았다. 2. 감조구간내(感潮區間內)에는 해수(海水)의 영향(影響)으로 인(因)하여 약(約) 270만(萬)$m^3$ 이상(以上)의 물이 저류(貯溜)되고 있으며 이중에서 염분농도(鹽分濃度)가 $750{\mu}{\mho}/cm$ 이하(以下)로써 관개용수(灌漑用水)로 이용(利用) 가능한 수량(水量)은 약(約) 120 만(萬)톤에 달(澾)하고 있다. 3. 해수침투현상(海水浸透現象)은 간만(干滿)의 차(差)에 의한 수위변화(水位變化)는 작으나 만조시(滿潮時) 염분침입(鹽分侵入)이 탁월(卓越)하여 뚜렷한 층(層)이 형성(形成)되는 성층밀도류(成層密度流)가 되고 간조시(干潮時)에는 염수(鹽水)쐐기가 후퇴(後退)하면서 쐐기 상류단(上流端)의 염분(鹽分)이 담수(淡水)와 혼합확산(混合擴散)되면서 유하(流下)하여 잘 혼합(混合)된 하구(河口)를 형성(形成)한다. 4. 염수(鹽水)쐐기의 길이는 5.9km로 계산(計算)되었으나 실제로는 4.4km지점(地點)에 설치(設値)된 연일(延日) 잠수교(潛水橋)의 영향(影響)으로 인(因)하여 동지점(同地點)에서 $S=320{\mu}{\mho}/cm$로써 염수(鹽水)의 침투(浸透)가 중단(中斷)된다. 5. 담수(淡水)와 해수(海水)사이에 어떠한 크기의 밀도차(密度差)가 존재(存在)하는 한(限) 수로(水路)바닥을 따라 흐르는 순상류(純上流) 방향(方向)의 흐름이 존재(存在)한다.

• Nuclear Engineering and Technology
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• 제42권6호
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• pp.662-669
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• 2010

To develop the manufacturing methods for the blanket first wall (FW) of the International Thermonuclear Experimental Reactor (ITER) and to verify the integrity of the joint, Be/Cu mockups were fabricated and tested at the KoHLT-1 (Korea Heat Load Test facility), a graphite heater facility located at the Korea Atomic Energy Research Institute (KAERI). Since Be and Cu joining is the focus of the present study, the fabricated mockups had a CuCrZr heat sink joined with three Be tiles as an armor material, unlike the original ITER blanket FW, which has a stainless steel structure and coolant tubes. Hot isostatic pressing (HIP) was carried out at $580^{\circ}C$ and 100 MPa for 2 hours as the method for Be/Cu joining. Three interlayers, namely, $1{\mu}mCr/10{\mu}mCu$, $1{\mu}mTi/0.5{\mu}mCr/10{\mu}mCu$, and $5{\mu}mTi/10{\mu}mCu$ were applied as a coating to the Be tiles by a physical vapor deposition (PVD) method. A shear test was performed with the specimens, which were fabricated by the same methods as those used to fabricate the mockups. The average values were 125 MPa to 180 MPa, and the samples with the $1{\mu}mCr/10{\mu}mCu$ interlayer showed the lowest value. No defect or delamination was found in the joints of the mockups by the developed ultrasonic test using a flat-type probe with a 10 MHz frequency and a 0.25 inch diameter. High heat flux (HHF) tests were performed at $1.0\;MW/m^2$ heat flux for each mockup using the given conditions, and the results were analyzed by ANSYS-CFX code. For the test criteria, an expected fatigue lifetime about 1,000 cycles was obtained by analysis with ANSYS-mechanical code. Mockups using the interlayers of $1{\mu}mTi/0.5{\mu}mCr/10{\mu}mCu$ and $5{\mu}mTi/10{\mu}mCu$ survived up to 1,100 cycles over the required number of cycles. However, one of the Be tiles in the other two mockups using the $1{\mu}mCr/10{\mu}mCu$ interlayer was detached during the screening test, and others were detached by discharge after 862 cycles. The integrity of the joints using the proposed interlayers was proven by the HHF test, but the other interlayer requires more study before it can be used for the joining of Be to Cu. Moreover, it was confirmed that the measured temperatures agreed well with the analysis temperatures, which were used to estimate the lifetime and that the developed facility showed its capability of the long time operation.

• Nuclear Engineering and Technology
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• 제42권4호
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• pp.442-449
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• 2010

Recently, the neutron irradiation for large diameter silicon (Si)-ingots of more than 8" diameter is requested to satisfy the demand for the neutron transmutation doping silicon (NTD-Si). By increasing the Si-ingot diameter, the radial non-uniformity becomes larger due to the neutron attenuation effect, which results in a limit of the feasible diameter of the Si-ingot. The current evaluation method has a certain limit to precisely evaluate the radial uniformity of Si-ingot because the current evaluation method does not consider the effect of the Si-ingot diameter on the radial uniformity. The objective of this study is to propose a new evaluation method of radial uniformity by improving the conventional evaluation approach. To precisely predict the radial uniformity of a Si-ingot with large diameter, numerical verification is conducted through comparison with the measured data and introducing the new evaluation method. A new concept of a gradient is introduced as an alternative approach of radial uniformity evaluation instead of the radial resistivity gradient (RRG) interpretation. Using the new concept of gradient, the normalized reaction rate gradient (NRG) and the surface normalized reaction rate gradient (SNRG) are described. By introducing NRG, the radial uniformity can be evaluated with one certain standard regardless of the ingot diameter and irradiation condition. Furthermore, by introducing SNRG, the uniformity on the Si-ingot surface, which is ignored by RRG and NRG, can be evaluated successfully. Finally, the radial uniformity flattening methods are installed by the stainless steel thermal neutron filter and additional Si-pipe to reduce SNRG.