• 한국막학회:학술대회논문집
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• 한국막학회 2004년도 Proceedings of the second conference of aseanian membrane society
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• pp.29-32
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• 2004

Reduction of methanol crossover in proton exchange membranes (PEMs) can be achieved by 1) the selection of materials, 2) the morphology control, and 3) the adequate crosslinking [1, 2]. The selection of polymer matrix of PEM for direct methanol fuel cells (DMFCs) is very important because the proton conductivity and methanol permeability are largely dependent upon the properties of polymers.(omitted)

• 전기화학회지
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• 제11권1호
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• pp.42-46
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• 2008

연료전지는 수소를 직접 사용하는 것이 가장 효율이 높지만 가정이나 사무실에서는 수소 저장탱크를 사용하기보다는 도시가스(메탄가스)를 연료 source로 하여 수소를 생산하는 것이 유리하다. 연료전지에 사용하는 수소는 천연가스나 바이오가스, 탄화수소계열의 연료를 개질하여 생산하며 개질반응과정에서 필연적으로 여러 성분의 불순물이 포함되어 있다. CO, $CO_2$, $H_2S$, $NH_3$, $CH_4$등의 불순물이 포함된 수소연료가 PEM fuel cell에 공급되면 연료전지 성능에 영향을 준다고 보고되어 있다. 이러한 영향에는 전극 촉매의 피독에 의한 kinetic losses, 전해질막과 촉매이온층의 양이온 전도성 감소에 의한 ohmic losses 그리고 촉매층의 구조나 소수성 감소에 의한 mass transport losses가 있다. 개질기에서 생산된 수소연료는 약 73%의 $H_2$와 20% 이하의 $CO_2$, 5.8% 이하의 $N_2$, 2% 이하의 $CH_4$, 10ppm 이하의 CO로 최종 공급된다. 본 연구에서는 연료 중에 $CO_2$가 고분자전해질 연료전지 anode측 성능에 미치는 영향을 조사하였다. 실험은 연료전지에 공급되는 연료중에 $CO_2$농도를 10%, 20%, 30%로 전류와 전압의 성능곡선과 장시간(10시간)실험 그리고 임피던스를 측정하였다. 또한 가스크로마토그래피를 이용하여 순수한 수소와 $CO_2$가 함유된 수소의 혼합을 통해 나온 연료전지 inlet에서의 불순물의 농도를 검증하였다.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2006년도 춘계학술대회 논문집
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• pp.369-370
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• 2006

During demonstrations of a process conditioning spent nuclear fuels, it is necessary to transport and handle Spent fuel road cuts from Post Irradiation Examination facility to Slitting device in The hot cell. the spent fuel pellets which are highly radioactive materials are separated with its clad and are fed into the next conditioning process. For this, a spent fuel rod, 3.5 m long, is cut by 25 cm long which is suitable length for the decladding process. These rod-cuts are packed into the capsule and are moved to the ACPF(Advanced spent nuclear fuel Conditioning Process Facility). In the ACPF, Once the capsule is unloaded in the ACPF, Capsule is taken out one-by-one and installed on the decladding device. In these processes, the crushed spent fuel pellet can be scattered inside the facilities and thus it contaminate the hot cell. In this paper, we developed the specially designed transportation and storage device for spent nuclear fuel capsules.

• Nuclear Engineering and Technology
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• 제47권1호
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• pp.85-93
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• 2015

Background: $^{241}Am$, $^{243}Am$, and $^{237}Np$ isotopes are among the most radiotoxic components of spent nuclear fuel. Recently, researchers have planned different incineration scenarios for the highly radiotoxic elements of nuclear waste in critical reactors. Computational methods are widely used to predict burnup rates of such nuclear wastes that are used under fuel matrixes in critical reactors. Methods: In this work, the Monte Carlo N-particle transport code was used to calculate the neutronic behavior of a transuranic (TRU)-bearing CANada Deuterium Uranium 6 reactor. Results: The computational data showed that the 1.0% TRU-containing thorium-based fuel matrix presents higher proliferation resistance and TRU depletion rate than the other investigated fuel Matrixes. The fuel matrix includes higher negative temperature reactivity coefficients as well. Conclusion: The investigated thorium-based fuel matrix can be successfully used to decrease the production of highly radiotoxic isotopes.

• 신재생에너지
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• 제3권3호
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• pp.14-19
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• 2007

A flow channel model of a bipolar plate with varying cross-sectional area was newly designed for improving performance and efficiency of a PEM fuel cell stack. As a result, the varying cross-sectional area model showed poor uniformity in velocity distribution, however, maximum velocity in the flow path is about 30% faster than that of the uniform cross-sectional area model. The proposed varying cross-sectional area model is expected to diffuse operating fluids more easily into diffusion layer because it has relatively higher values in pressure distribution compared with other flow channel models. It is expected that the implementation of the varying cross-sectional area model can reduce not only the mass transport loss but also the activation loss in a PEM fuel cell, and open circuit voltage of a fuel cell can thus be increased slightly.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(2)
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• pp.847-852
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• 1995

A shielding analysis for KSC-7, the shipping cask for transporting the 7 PWR spent fuel assemblies, has been carried out. Radiation source term has been calculated on spent fuel with burnup of 50,000 MWD/MTU and 1.5 years cooling time by ORIGEN2 code. The shielding calculation for the cask has been made by using MCNP4A code with continuous cross section data library from ENDF/B-V. As a result of neutron dose rate analysis, another shielding calculational model on spent fuel shipping cask was provided which is using the Monte Carlo method.

• 한국연소학회:학술대회논문집
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• 한국연소학회 2013년도 제46회 KOSCO SYMPOSIUM 초록집
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• pp.83-85
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• 2013

With an increase in the use of low rank coals in power plants, various operational issues were raised in the fuel storage and supply, combustion, boiler and flue gas treatment systems. In the fuel storage and supply system, the main issue is the self-heating propensity of low rank coals leading to spontaneous combustion in yard storage, transport and pulverization. This study evaluated the reactivity of various sub-bituminous and bituminous coals with oxygen at low temperatures by analyzing the temperature increase characteristics of coals under a constant flow rate of oxygen supply. The results were quantified to a self-heating index and the relation with the fuel properties were evaluated.

• 한국해양공학회지
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• 제37권5호
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• pp.181-189
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• 2023

The fuel consumption of marine diesel engines holds paramount importance in contemporary maritime transportation and shapes energy efficiency strategies of ocean-going vessels. Nonetheless, a noticeable gap in knowledge prevails concerning the influence of ship hull conditions and propeller roughness on fuel consumption. This study bridges this gap by utilizing artificial intelligence techniques in Matlab, particularly convolutional neural networks (CNNs) to comprehensively investigate these factors. We propose a time-series prediction model that was built on numerical simulations and aimed at forecasting ship hull and propeller conditions. The model's accuracy was validated through a meticulous comparison of predictions with actual ship-hull and propeller conditions. Furthermore, we executed a comparative analysis juxtaposing predictive outcomes with navigational environmental factors encompassing wind speed, wave height, and ship loading conditions by the fuzzy clustering method. This research's significance lies in its pivotal role as a foundation for fostering a more intricate understanding of energy consumption within the realm of maritime transport.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1439-1447
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• 2023

The fuel cycle characteristics of the IVG.1M reactor were studied within the framework of the research reactor conversion program to modernize the IVG.1M reactor. Optimum use of the nuclear fuel and reactor was achieved through routine methods which included partial fuel reloading combined with scheduled maintenance operations. Since, the additional problem in planning the fuel cycle of the IVG.1M reactor was the poisoning of the beryllium parts of the core, reflector, and control system. An assessment of the residual power and composition of spent fuel is necessary for the selection and justification of the technology for its subsequent management. Computational studies were performed using the MCNP6.1 program and the neutronics model of the IVG.1M reactor. The proposed scheme of annual partial fuel reloading allows for maintaining a high reactor reactivity margin, stabilizing it within 2-4 β_eff for 20 years, and achieving a burnup of 9.9-10.8 MW × day/kg U in the steady state mode of fuel reloading. Spent fuel immediately after unloading from the reactor can be placed in a transport packaging cask for shipping or safely stored in dry storage at the research reactor site.

• 한국항공우주학회지
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• 제42권8호
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• pp.713-721
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• 2014

현재 유럽과 미국에서는 각각 GRC(Green Rotorcraft) 와 SRW (Subsonic Rotary Wing program) 프로그램을 통하여 차세대 회전익기 개발이 진행 중에 있다. 이들 프로그램의 최종 목적은 현재 사용 중에 있는 단거리 여객기를 일부 대체 할 수 있는 틸트로터 타입의 중/소형 민간 회전익기 개발에 목적을 두고 있다. 또한 이들 틸트 로터의 민간 운영에 운영할 수 있는 안전한 운행을 위하여, 각각 개발 중인 air transport management(ATM) 시스템인 SESAR(Single European Sky ATM Research) 와 NextGen(Next Generation Air Transport System)과 융합하는 기술도 병행되고 있다. 이들 프로그램들은, 최종 목표인 틸트 로터기의 개발이 진행되는 중간 과정으로, 현재 사용되고 있는 헬리콥터의 성능의 향상도 병행하고 있다. 이러한 성능 개발은 좀 더 효율적인 추진기관, 능동 로터 시스템, 내/외부의 소음 감소 등에 중점을 두고 있다. 특히 유럽의 GRC 프로그램에서는 소음, 연료소비율, 배기가스 (CO2, NOx)의 절감 등에 매우 구체적인 목표를 설정하여 기술 개발을 진행 중에 있다.