• Journal of Advanced Navigation Technology
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• v.15 no.6
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• pp.994-999
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• 2011

This paper explains how existing electrical ADU(Antenna Distribution Unit) has been improved into a mechanical ADU. Generally the mechanical ADU has stabilized Glide Path which provides a RF signal to the aircraft for safe landing and it has solved the issue of phase shift and power distribution ratio change which can be occurred during long-term use. Besides it has been certified by Flight check and operating several airports in oversea as well as in korea.

• Nuclear Engineering and Technology
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• v.48 no.1
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• pp.175-181
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• 2016

This study investigates the dispersibility of carbon in carbon contained ammonium diuranate (C-ADU) gel particles and the characteristics of C-ADU gel liquid droplets produced by the vibrating nozzle and integrated aging-washing-drying equipment. It was noted that the excellent stability of carbon dispersion was only observed in the C-ADU gel particle that contained carbon black named CB 10. ADU gel liquid droplets containing carbon particles with the excellent sphericity of approximately 1,950 mm were then obtained using an 80-100-Hz vibrating nozzle system. Dried C-ADU gel particles obtained by the aging-washing-drying equipment were thermal decomposed until $500^{\circ}C$ at a rate of $1^{\circ}C/min$ in an air or in 4% $H_2$ gas atmosphere. The thermally decomposed C-ADU gel particles showed 24% weight loss and a more complicated profile than that of ADU gel particles.

• Proceedings of the Korean Association of Geographic Inforamtion Studies Conference
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• 2000.11a
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• pp.49-53
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• 2000

• Proceedings of the Korean Association of Geographic Inforamtion Studies Conference
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• 2000.11a
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• pp.67-70
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• 2000

• Nuclear Engineering and Technology
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• v.49 no.3
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• pp.541-548
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• 2017

Uranium metal used for fabrication of fuel for research reactors in India is generally produced by magnesio-thermic reduction of $UF_4$. Performance of magnesio-thermic reaction and recovery and quality of uranium largely depends on properties of $UF_4$. As ammonium diuranate (ADU) is first product in powder form in the process flow-sheet, properties of $UF_4$ depend on properties of ADU. ADU is generally produced from uranyl nitrate solution (UNS) for natural uranium metal production and from uranyl fluoride solution (UFS) for low enriched uranium metal production. In present paper, ADU has been produced via both the routes. Variation of uranium recovery and crystal structure and composition of ADU with progress in precipitation reaction has been studied with special attention on first appearance of the precipitate Further, ADU produced by two routes have been calcined to $UO_3$, then reduced to $UO_2$ and hydroflorinated to $UF_4$. Effect of two different process routes of ADU precipitation on the characteristics of ADU, $UO_3$, $UO_2$ and $UF_4$ were studied here.

• KIPE Magazine
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• v.9 no.3
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• pp.23-27
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• 2004

ADuC84x는 OP-AMP 아날로그-디지털 컨버터(ADC), 디지털-아날로그 컨버터(DAC)로 유명한 ADI(아날로그 디바이스사)의 8비트 임베디드 마이크로콘트롤러인 마이크로컨버터이다. ADI의 마이크로컨버터 ADuC84x는 산업용 정밀제어 및 계측용 애플리케이션의 고성능 신호처리를 위해 설계된 프로그래머블 고속 임베디드 마이크로콘트롤러이다.(중략)

• Proceedings of the Korean Institute of Intelligent Systems Conference
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• 2004.04a
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• pp.261-264
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• 2004

컴퓨터 전략 시뮬레이션 게임 설계에서는 Master ADU(Artificial Decision Unit)의 전략 수립을 위한 방법으로 다양한 기법들이 연구되고 있다. 특히 한정된 자원 하에서 게임을 사실적이고 지적인 기능을 구현하기 위해 치팅(Cheating)을 활용하거나 간단한 인공지능 기법이 적용되고 있다. 하지만 이 기법들은 사용자 적응성 및 전략 수립의 단순성을 야기하는 단점을 가지고 있다. 본 연구에서는 전략 시뮬레이션 게임의 전략 수립 에이전트인 Master ADU(Artificial Decision Unit)를 위하여 셀룰라 오토마타의 초기 규칙 생성에 유전자 알고리즘의 교배 및 돌연변이, 적합도 평가를 거친 유전자 형을 적용한 혼합형 전략 수립 기법을 제안한다 이 기법은 ADU가 적합한 유전자 형을 생산 및 선택하여 사용자에 대해 적극적으로 학습할 수 있었다.

• Journal of The Korean Astronomical Society
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• v.37 no.4
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• pp.185-191
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• 2004

We have been developing a solar observing system based on a fast CCD camera 1M30P made by the DALSA company. Here we examine and present the characteristics and performance of the camera. For this we have analyzed a number of images of a flat wall illuminated by a constant light source. As a result we found that in the default operating mode 1) the mean bias level is 49 ADU/pix, 2) the mean dark current is about 8 ADU /s/pix, 3) the readout noise is 1.3 ADU, and 4) the gain is about 42 electrons/ ADU. The CCD detector is found to have a linearity with a deviation smaller than $6\%$, and a uniform sensitivity better than $1\%$. These parameters will be used as basic inputs in the analysis of data to be taken by the camera.

• Proceedings of the Korean Association of Geographic Inforamtion Studies Conference
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• 2000.11a
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• pp.42-48
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• 2000

• Applied Chemistry for Engineering
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• v.8 no.1
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• pp.99-107
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• 1997

This study Provides the treatment methods of liquid wastes from the dissolution/purification process of nuclear fuel raw material and the fabrication process of nuclear fuel powder. One of the treatment methods is to process liquid waste from uranium raw material dissolution/purification process. This waste, of the strong acid, can be reused to dissolve the fine ADU particles in filtrate which is ADU waste of pH 8.0 converted from AUC waste after recovery of uranium. To dissolve the fine ADU particles, ADU filtrate was pretreated to pH 4.0 with the dissolution/purification waste, and then mixed with the lime to pH 9.2 and aged for 30 minutes. From this processing, uranium content of the filtrate was decreased to below 3ppm. The waste from fuel powder fabrication is emulsified solution dispersed with fine oil droplets. This emulsion was destroyed effectively by adding and mixing the nitric acid with rapid heating at the same time. After this processing, $Na_2U_2O_7$ compound is produced by addition of NaOH. Optimum condition of this processing was shown at pH 11.5, and uranium content of the filtrate was analyzed to 5ppm. To remove the trace of uranium in the filtrate, lime should be added. Otherwise, 4N nitric acid was used to destroy the emulsion directly, and then lime was added to this waste. Uranium content of the treated filtrate was below 1 ppm. In addition to these wastes, the trace of uranium in filtrate after recovery of uranium from the AUC waste which is produced during PWR power preparation, is treated with NaOH to takeup fluorine(F) in the waste because fluorine is valuable and toxic material. In the finally treated waste, uranium was not detected.