• 방사성폐기물학회지
• /
• 제2권2호
• /
• pp.125-133
• /
• 2004

최대 선출력 61 ㎾/m 및 평균 연소도 1,770 ㎿d/tU의 조건으로 하나로에서 조사한 DUPIC(Direct Use of Spent PWR Fuel in CANDU Reactors) 핵 연료를 EPMA (Electron Probe Micro Analyzer)를 이용하여 핵분열 생성물을 분석하였다. EPMA의 정확한 분석 방법을 확립하고자, 핵분열생성물 대신 시약을 첨가하여 제조한 모의 DUPIC 핵연료로 EPMA 분석을 수행하였고, 그 결과를 습식 화학 분석의 결과와도 비교하여 평가하였다. 모의 DUPIC 핵연료 중심부의 금속 석출물은 약 1 $\mu\textrm{m}$ 정도의 크기로 관찰되었으며, 이들의 조성은 Mo-53.89 at.%, Ru-37.40 at.% 및 Pd+Rh-8.71 at%이었다. 모의 DUPIC 핵연료 시험에서 정립한 시험방법으로 조사한 DUPIC 핵연료 시편의 금속 석출물 특성을 분석하였다. 핵연료 중앙부에서 관찰된 금속 석출물들의 크기는 2∼2.5 $\mu\textrm{m}$ 정도이었으며, Mo-47.34 at.%, Ru-46 at.%, Pd+Rh-6.65 at.%의 조성임을 확인하였다. 이 실험을 위하여, 특별히 시료의 전도성을 향상시키기 위한 처리를 하였으며, 작은 금속 석출물에 EPMA의 전자빔을 정확히 조사할 수 있는 실험 조건을 제시하였다.

• Korean Chemical Engineering Research
• /
• 제49권4호
• /
• pp.423-431
• /
• 2011

최근 대체에너지에 대한 관심이 높아짐에 따라 수소에너지를 기반으로 하는 차세대 발전 장치인 연료전지 관련 기술 개발이 활발하게 이루어지고 있다. 특히, 고온 연료전지의 대표적인 형태인 용융 탄산염 연료전지(MCFC: Molten Carbonate Fuel Cell, 이하 MCFC)는 전력사업용으로의 높은 가능성을 인정받아 화석연료를 대체할 발전방식으로 평가 받고 있다. 본 연구에서는 Aspen Custom Modeler($ACM^{TM}$)에서 평형반응식을 이용하여 스택 모델을 구성한 후, Aspen $Plus^{TM}$에서 BOP(Balance of Plant) 시스템과 스택을 연결하여 전체 MCFC 발전 시스템의 정상상태를 모사하였다. 모델의 유효성을 입증하기 위해서 전류밀도, 연료이용률, S/C ratio, 재순환 흐름 비와 같은 주요 조업변수에 따른 셀 전압, 전력, 효율 등 시스템의 성능을 분석하였다. 그리고 Aspen $Dynamics^{TM}$에서 PID제어 방식을 적용하여 제어루프를 구성하였고 부하변화, 설정점 변화, 재순환 흐름비 변화에 따른 각각의 사례연구를 통하여 전체 시스템의 성능변화를 예측하였다. 그 결과 연료이용률과 전류밀도의 변화에 따른 전체 시스템의 최대 발전 효율 및 출력전압을 위한 운전조건을 제안하였다.

• 대한기계학회논문집B
• /
• 제33권5호
• /
• pp.373-380
• /
• 2009

The evaporation process of multi-component fuel is different from one of a single component, because the properties of each component affects among the components. In actual engine, the spatial distribution of fuel vapor concentration dominates auto-ignition and initial combustion, and depends on the volatility and diffusivity of each component fuel contained in the multi-component fuel. Then, this study proposes a simplified numerical scheme for analysis of evaporation process of multi-component fuel sprays. Evaporation process is calculated by KIVA-II code based on the simple two-phases region that is approximated by modified saturated liquid-vapor line, which was obtained by connecting the 50% distillation temperature for each component under several pressure fields. Consequently, it can be quantitatively simulated that vapor of low boiling fuel component mostly exists around nozzle and spray tip region, the high boiling duel component, on the other hand, mostly appears near the spray tip.

• 한국항해항만학회지
• /
• 제35권8호
• /
• pp.637-641
• /
• 2011

해양구조물 전력시스템은 독립형 전력체계를 구축하기 어렵다. 그러므로 해상용 전력시스템을 효과적으로 운영하기 위하여 연료전지 및 하이브리드 전력체계를 연동한 전력시스템을 구축하는 것이 중요하다. 본 연구에서는 연료전지 기반의 해양구조물용 전력체계 설계에 필요한 수소 발생 메카니즘, 사용 전력량 계산과정 등을 기초로 해상용 연료전지 기반의 전력체계를 설계하고, 설계된 전력 시스템을 LabVIEW 프로그램을 활용하여 시뮬레이션 및 분석하였으며, 이를 기반으로 해양구조물용 전력시스템 설계 방안을 제안하고자 한다.

• 한국자동차공학회논문집
• /
• 제5권5호
• /
• pp.51-66
• /
• 1997

A heat transfer model of the intake valve in a spark ignition engine is presented, which is calibrated with a number of the valve temperature profiles measured during engine warm-up for the gaseous fuel(propane). The valve is divided into four identical elements for which the assumption of lumped thermal mass is applied. The calibration is made so that the difference between the measued and simulated valve temperatures becomes minimal. Then the model is applied to the cases of the liquid fuel(indolene) to estimate the amount of the liquid fuel vaporized from the intake valve by assuming that fuel evaporation accounts for the deficit of the heat balance budget. The results of the model show quantitative contribution of each heat transfer source to the heat balance. The behavior of the calculated mass fraction of the fuel vaporized from the intake valve explains how the liquid fuel evaporate during engine warm-up. The mass fraction at warmed-up condition is closely related with the fraction directly targeted on the valve back by the fuel spray geometry.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
• /
• pp.191-204
• /
• 2004

The research and development of effective management technologies of the spent fuels discharged from power reactors are an important and essential task of KAERI. In resent several years KAERI has focused on a project named "development and demonstration of the Advanced spent fuel Conditioning Process (ACP) in a laboratory scale." The Facility for ACP demonstration consists of two Hot Cells and auxiliary facilities. It is now in the final design stage and will be constructed in 2004. After construction of the facility the ACP equipments will be installed in Hot Cells. The ACP will be demonstrated by some simulated spent fuels first and then by spent fuels.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
• /
• pp.169-174
• /
• 1998

An 1200-day time-dependent fuel-management for the transition from 37-element fuel to CANFLEX-NU fuel in a CANDU 6 reactor has been simulated to show the compatibility of the CANFLEX-NU fuel with the reactor operation. The simulation calculation were carried out with the RFSP code, provided by cell averaged hel properties obtained from the POWDERPUFS-V code. The refueling scheme for both fuels was an eight bundle shift art a time. The simulation results show that the maximum channel and bundle powers were maintained below the licence limit of the CANDU 6. This indicates that the CANFLEX-NU fuel bundle is compatible with the CANDU 6 reactor operation during the transition period.

• 한국수소및신에너지학회논문집
• /
• 제14권3호
• /
• pp.236-246
• /
• 2003

This paper focuses on developing a model of a PEM fuel cell stack and to integrate it with realistic model of the air supply system for fuel cell vehicle application. The fuel cell system model is realistically and accurately simulated air supply operation and its effect on the system power and efficiency using simulation tool Matlab/Simulink. The Peak performance found at a pressure ratio of 3, and it give a 15mV increase per cell. The limit imposed is a minimum SR(Stoichiometric Ratio) of 2 at low fuel cell load and 2.5 at high fuel cell load.

• 한국기계가공학회지
• /
• 제11권6호
• /
• pp.123-129
• /
• 2012

This study was carried out to improve the design of fuel injection pump for marine medium diesel engine. For this purpose, all parts of fuel injection pump were modeled and simulated using CATIA V5R19, FLUENT & MSC Nastran. Flow analysis for plunger cylinder and structural analysis for plunger, roller and spring, which were considered as essential parts of fuel injection pump, were performed to find the optimal design of fuel injection pump. As the results, flow of fluid in plunger cylinder was showed good results in case of 7.7~8.0m/s of plunger velocity. Furthermore, it was confirmed that plunger, roller and spring could be operated safely under 1,800bar pressure.

• Nuclear Engineering and Technology
• /
• 제50권7호
• /
• pp.1190-1197
• /
• 2018

Analysis of the GRSW-A model coupled into the FALCON code is extended by simulation of central void formation in fuel pellets due to high-temperature fuel restructuring. The extended calculation is verified against published, well-known experimental data. Good agreement with the data for a central void diameter in pellets of the rod irradiated in an Experimental Breeder Reactor is shown. The new calculation methodology is employed in comparative analysis of modern BWR fuel behavior under assumed high-power operation. The initial fuel porosity is shown to have a major effect on the predicted central void diameter during the operation in question. Discernible effects of a central void on peak fuel temperature and Pellet-Cladding Mechanical Interaction (PCMI) during a simulated power ramp are shown. A mitigating effect on PCMI is largely attributed to the additional free volume in the pellets into which the fuel can creep due to internal compressive stresses during a power ramp.