디지털 시대에 가상현실 콘텐츠 속에서 일루젼으로 표현된 공간의 연구에 의한 실제 공간의 재해석을 해야 하는 필요성이 강조되고 있다. 가상현실 디자인에서 콘텐츠에 연관하여 일루젼과 시각적 사고의 관계를 비 교해 보면 대부분 가상현실 콘텐츠가 갖는 근본적인 성질임을 알 수 있다. 또한 사용자들은 가상현실 콘텐 츠의 특성에 따라 시지각적 일루젼을 체험하며 사용자들의 시각적 인지에 경험을 할 수 있는 중요한 디자 인 구성요소가 된다. 본 연구는 가상현실 콘텐츠의 시각적 환영의 조건에 대해 분석하고 이를 바탕으로 가 상현실 콘텐츠에 적용된 재현적 환영 표현을 연구하는데 목적이 있다. 따라서 본 연구는 가상현실의 개념과 분류를 알아보고, 시각적 일루젼의 조건을 정립하는 것으로 부터 시작한다. 또한 선행연구와 기존문헌 토대 로 가상현실에 적합한 시각적 일루젼의 조건을 분류하였다. 시각적 일루젼의 조건은 시지각적 일루젼의 조 건, 공간적 일루젼의 조건, 재현적 일루젼의 조건 3가지의 조건으로 분류하였으며, 과거 미술사 속에 10가지 의 세부적인 시각적 일루젼 형태로 분류된다. 이를 바탕으로 가상현실 콘텐츠인 미디어아트, 아트 게임와 가상현실 게임을 선정하여 콘텐츠 사례를 분석하고 결과를 산출하였다.

To precisely assemble the fuel test rod, an orbital TIG welding system was designed and developed to accurately conduct orbital TIG welding for the nuclear fuel test rod. Using this system, a welding process needs to confirm the welding properties for orbital TIG welding. Therefore, preliminary weld tests were performed on the cladding tubes under various conditions, and the results show that the width and depth of HAZ of the cladding specimen welded using identical power during an orbital TIG welding cycle was continuously increased from a welded start-point to a welded end-point because of heat accumulation. The performance tests were conducted under the welding conditions considered through preliminary welding tests, and the properties of the specimens were conformed through surface and microstructure analyses.

To conduct a nuclear fuel irradiation test, the inside of the nuclear fuel rod must be assembled along with the test fuel, several different parts, and sensors, and then filled with high-pressure and high-purityhelium gas. Therefore, it is necessary to develop helium gas filling techniques that can achieve exact TIG (Tungsten Inert Gas) spot welding at a pin-hole of the nuclear fuel rod to fill helium gas into the nuclear fuel test rod. However, previous apparatuses do not have repeatability for TIG spot welding as they lack an electrode position control jig to exactly fix a TIG electrode in a high-pressure chamber, and they consume a large amount of helium gas. Therefore, a TIG spot welding apparatus was developed to easily and accurately conduct TIG spot welding and significantly reduce the gas consumption. In addition, the optimum welding conditions of this welding apparatus were established through various weld tests.

Fiber laser welding has been developed for precise welding of small and complicate components assembled on the nuclear fuel irradiation test rig. In this research, laser welding characteristics of STS316L, the main material of nuclear fuel test rig, have been studied. Several welding experiments were carried out in lap welding of the tube and the end cap made of STS316L. Process variables such as non-focal length, shield gas, laser frequency and power are optimized and compared with the results of Zircaloy-4.

When a new nuclear fuel is developed, irradiation test needs to be carried out in the research reactor to analyze the performance of the new nuclear fuel. It is necessary to attach sensors in the fuel rod and connect them with instrumentation cables to check the performance of the nuclear fuel during the burn up test in the test loop. A thermocouple is installed at the center of the fuel rod to check the centerline temperature of a fuel rod during the irradiation test. Therefore, A hole needs to be made at the center of a fuel pellet to put the thermocouple. However, it is difficult to make a small fine hole on the sintered UO2 pellet with a simple drilling machine, because the hardness and density of a sintered UO2 pellet are very high. In this study, an instrumented fuel rod mock-up was fabricated using an automated precise drilling machine. Four sintered alumina were drilled off and assembled into the zircaloy tube and a thermocouple was instrumented in the fuel rod mock-up. Sealing of an instrumented fuel rod mock-up was performed in the following two methods. It is sealing of similar metals perform by welding method, and sealing of dissimilar metals perform by swagelok method.

Fuel Test Loop(FTL) is a facility which could conduct a fuel irradiation test at HANARO (High-flux Advanced Neutron Application Reactor). FTL simulates commercial NPP’s operating conditions such as the pressure, temperature and neutron flux levels to conduct the irradiation and thermo- hydraulic tests. The In-Pile Test Section(IPS) installed in HANARO FTL is designed as a pressure vessel design conditions of 350℃, 17.5MPa. The instrumentation MI-cables for thermocouples, SPND and LVDT are passed through the sealing plug, which is in the pressure boundary region and is a part of instrumentation feedthrough of MI-cable. In this study, the brazing method and performance test results are introduced to the sealing plug with BNi-2 filler metal, which is selected with consideration of the compatibility for the coolant. The performance was verified through the insulation resistance test, hydrostatic test, and helium leak test.

Fuel test loop is an irradiation test facility which can conduct the irradiation tests of nuclear fuels and materials at HANARO. The FTL simulates the operating conditions of commercial nuclear power plants such as their pressure, temperature, flow and water chemistry to conduct the irradiation and thermo-hydraulic tests. The passivation of the fuel test loop was performed for the main cooling system in the commissioning stage with satisfaction of the operation criterion such as temperature and water chemistry conditions. The experimental results show that the passivation was completed successfully.

It is necessary to examine the source contributions and the relationship between a receptor and sources for the resonable controlling of air pollution level of suspended particulate matters. Therefore, in this study, profiles of sources contributing to the concentration of suspended particulate matters, were developed and CMB model was applied to obtain information of source contributions and feasibility of CMB model application. According to the propose of this study, twenty-seven chemical species such as the elements, anions, and total carbon of thirty-six PM_10 and TSP data sets sampled at the Poˇmch`oˇn receptor site in Pusan for a 24-hr period from May to Aug. 1992, were analyzed and three (transportation, soil, marine) different source profiles were developed through the field measurement. Applying CMB model to transportation, soil, marine, the results of source contribution by CMB model showed that the case with TSP was more suitable for CMB model than that with PM_10. And the average contribution of transportation source to TSP and PM_10 concentration at Poˇmch`oˇn receptor was calculated as 90.66 ㎍/㎥(64%) and 23.27 (㎍/㎥(39%), respectively, which showed that the contribution by transportation was dominant. The validation of CMB model was performed by means of the results of contributions from marine source for the wind direction sectors.