• 전기학회논문지
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• 제67권6호
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• pp.745-752
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• 2018

ICs(Integrated circuits) for nuclear power plant exposed to radiation environment occur malfunctions and data errors by the TID(Total ionizing dose) effects among radiation-damage phenomenons. In order to protect ICs from the TID effects, this paper proposes a radiation-hardening of the logic circuit(D-latch) which used for the data synchronization and the clock division in the ICs design. The radiation-hardening technology in the logic device(NAND) that constitutes the proposed RH(Radiation-hardened) D-latch is structurally more advantageous than the conventional technologies in that it keeps the device characteristics of the commercial process. Because of this, the unit cell based design of the RH logic device is possible, which makes it easier to design RH ICs, including digital logic circuits, and reduce the time and cost required in RH circuit design. In this paper, we design and modeling the structure of RH D-latch based on commercial $0.35{\mu}m$ CMOS process using Silvaco's TCAD 3D tool. As a result of verifying the radiation characteristics by applying the radiation-damage M&S (Modeling&Simulation) technique, we have confirmed the radiation-damage of the standard D-latch and the RH performance of the proposed D-latch by the TID effects.

• Nuclear Engineering and Technology
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• 제41권6호
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• pp.785-796
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• 2009

A KALIMER-600 concept which is a type of sodium-cooled fast reactor, has been developed at KAERI. It uses sodium as a primary coolant and is a pool-type reactor to enhance safety. Also, a supercritical carbon dioxide ($CO_2$) Brayton cycle is considered as an alternative to an energy conversion system to eliminate the sodium water reaction and to improve efficiency. In this study, a simplified model for analyzing the thermodynamic performance of the KALIMER-600 coupled with a supercritical $CO_2$ Brayton cycle was developed. To develop the analysis model, a commercial modular modeling system (MMS) was adopted as a base engine, which was developed by nHance Technology in USA. It has a convenient graphical user interface and many component modules to model the plant. A new user library for thermodynamic properties of sodium and supercritical $CO_2$ was developed and attached to the MMS. In addition, some component modules in the MMS were modified to be appropriate for analysis of the KALIMER-600 coupled with the supercritical $CO_2$ cycle. Then, a simplified performance analysis code was developed by modeling the KALIMER-600 plant with the modified MMS. After evaluating the developed code with each component data and a steady state of the plant, a simple power reduction and recovery event was evaluated. The results showed an achievable capability for a performance analysis code. The developed code will be used to develop the operational strategy and some control logics for the operation of the KALIMER-600 with a supercritical $CO_2$ Brayton cycle after further studies of analyzing various operational events.

• 전기전자학회논문지
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• 제23권2호
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• pp.667-674
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• 2019

최근 발생한 원전 사고는 소외전원 및 비상전원의 기능이 상실되어 발전소 전체 정전이 발생한 사례를 계기로 원전의 비상전원공급용 배터리의 중요성이 부각되고 있다. 현재 원전의 비상전원공급용 배터리는 기존의 납축전지를 대신하여 리튬계열 배터리로 교체가 고려되고 있는 상황이다. 이에 따라 원통형 리튬 배터리의 적용성을 판단하기 위해 여러 가지 리튬 계열 배터리의 전기적 특성 실험을 진행하여 결과를 분석해야 한다. 본 논문은 현재 ESS(Energy Storage Systems)에 많이 사용되는 세 가지 타입의 리튬 배터리의 전기적 특성실험을 통해 적절한 배터리 타입을 선정하고, 선정된 배터리가 비상전원공급용 배터리로 사용될 때 최적의 C-rate를 제안한다. 또 배터리 모델링을 통해 배터리의 상태를 추정하며 문제점을 제시한다.

• Smart Structures and Systems
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• 제31권3호
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• pp.275-281
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• 2023

In recent years, technological developments have rapidly increased the number of complex structures and equipment in the industrial. Accordingly, the prognostics and health monitoring (PHM) technology has become significant. The safety assessment of industrial sites requires data obtained by installing a number of sensors in the structure. Therefore, digital twin technology, which forms the core of the Fourth Industrial Revolution, is attracting attention in the safety field. The research on digital twin technology of structures subjected to seismic loads has been conducted recently. Hence, this study proposes a digital twin system that estimates the responses and arbitrary load in real time by utilizing the minimum sensor to a pipe that receives a seismic and arbitrary load. To construct the digital twin system, a finite-element model was created considering the dynamic characteristics of the pipe system, and then updating the finite-element model. In addition, the calculation speed was improved using a finite-element model that applied the reduced-order modeling (ROM) technology to achieve real-time performance. The constructed digital twin system successfully and rapidly estimated the load and the point where the sensor was not attached. The accuracy of the constructed digital twin system was verified by comparing the response of the digital twin model with that derived by using the load estimated from the digital twin model as input in the finite-element model.

• Journal of Biosystems Engineering
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• 제34권5호
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• pp.342-350
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• 2009

Currently TMR feed produced in commercial plant is one of the major source to feed cattle for both beef and dairy farm. However, because of lack of cutting and mixing system for utilizing domestic produced firmly baled round roughage in commercial TMR plant, these commercial TMR feed can not satisfy to farmers both in quality and price points of view. In order to solve these problems, a farm group size TMR plant model was developed in this study. The model plant was consist of round bale receiving and cutting system, pneumatic conveying system for transfer the roughage which was cut at the cutter to TMR mixer through pneumatic conveyor, TMR mixer enable to soften the stiff rice strew and to mix with other ingredients, finished feed bin which can be transfer to either packing system or individual farm, packing system by tycon bag which contains 400 kg unit and bulk unloading system to individual farmer. Also, a simulation model ARENA was applied to the model system in order to evaluate and check the production rate in each unit process and operation rate of total system and to find out if there are any clogged unit system obstructing the smooth flow of the total process flow. Processing cycle for produce one batch of the model plant was less than 30 minutes. Thus, it will take less than four hours for producing 16 tons per day equivalent to 1,000 beef cattle's daily feed.

• 한국산학기술학회논문지
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• 제20권2호
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• pp.632-637
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• 2019

해양 플랜트 전장생산설계의 케이블 트레이 설계는 구조 부재 및 각종 의장 장비들과 간섭없이 케이블이 설치될 수 있도록 3D 모델링하여 원활하게 최적 배치하는 작업으로, 대부분 PDMS(Plant design management system)를 이용하여 수행되고 있다. PDMS는 해양 플랜트 생산설계 전용 3D CAD 시스템으로 국내 조선소와 관련 설계협력업체에서 널리 사용되고 있다. 본 연구에서는 PDMS 기반 해양 플랜트 케이블 트레이 설계 지원 PML(Programmable macro language)을 개발하여, 기존 방법 대비 업무 효율성을 검토하였다. 개발된 케이블 트레이 설계 PML은 전장 템프릿 라이브러리를 이용하여 완전히 파라메트릭 설계가 가능하도록 함으로써 설계 변경으로 인한 빈번한 수정 작업에 신속히 대응할 있도록 하였고, 축적된 설계 경험를 반영하여 반복되는 작업 피로를 최소화할 수 있도록 하였다. 그리고 개발된 시스템을 해양 플랜트 구조 모듈에 적용하여 기존 방법 대비 약 50% 이상의 작업 효율성 향상이 예상됨을 확인하였다.

• KEPCO Journal on Electric Power and Energy
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• 제2권3호
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• pp.415-419
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• 2016

As the need for clean coal technology has grown, so has the global research and development efforts into integrated gasification combined cycle (IGCC) plants. An IGCC plant couples a gas turbine to a gasification block. Various technical and economic problems exist in designing such a system. One such problem is the difficulty in realizing economies of scale because the single-train flow capacity of commercial IGCC synthetic gas turbine plants is limited; the capacity does not exceed a net power rating of 300 MW. To address this problem, this study modeled and simulated a synthetic gas turbine with the goal of evaluating the feasibility of a 500 MW or larger IGCC plant. First, a gas turbine with the best output and efficiency was chosen for use with natural gas. The turbine was modeled using GateCycle (a simulation tool), and the integrity of the model validated by comparing the result to the design value. Next, off-design modeling was carried out for a gas turbine with synthetic gas based on its on-design model, and the result was compared with the study result of the gas turbine manufacturer. The simulation confirmed that it is possible to create a large capacity IGCC plant by undertaking the remodeling of a gas turbine designed to use natural gas into one suitable for synthetic gas.

• 한국지능시스템학회논문지
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• 제7권2호
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• pp.43-50
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• 1997

쓰러기 소각로는 다음과 같은 불명확한 요소들을 포함한다. 즉 연료로 사용되는 쓰레기의 물리적 특성의변동 그리고 연소현상의 복잡성 등이다. 이것은 기존의 제어기법을 쓰레기의 연소제어에 적용하기가 매우 어렵게 만든다. 따라서 대부분의 쓰레기 소각로는 조작자의 운전에 의존한다. 본 논문에서는 쓰레기 소각로의 연소제어를 위한 다변수퍼지모델 예측제어를 제안한다. 쓰레기 소각로의 모델을 구하기 위해 적응 네트워크에 기초한 퍼자추론시스템이 사용되고 동정된 퍼지 모델을 이용하여 다변수 퍼지모델 예측제어기가 설계된다. 그리고 제안된 제어기의 성능을 평가하기 위해 컴퓨터 시뮬레이션이 수행되었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.641-646
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• 1998

In order to enhance the dynamic and interactive simulation capability of a system thermal hydraulic code for nuclear power plant, applicability of flow network models in SINDA/FLUIN $T^{™}$ has been tested by modeling feedwater system and coupling to DSNP which is one of a system thermal hydraulic simulation code for a pressurized heavy water reactor. The feedwater system is selected since it is one of the most important balance of plant systems with a potential to greatly affect the behavior of nuclear steam supply system. The flow network model of this feedwater system consists of condenser, condensate pumps, low and high pressure heaters, deaerator, feedwater pumps, and control valves. This complicated flow network is modeled and coupled to DSNP and it is tested for several normal and abnormal transient conditions such turbine load maneuvering, turbine trip, and loss of class IV power. The results show reasonable behavior of the coupled code and also gives a good dynamic and interactive simulation capabilities for the several mild transient conditions. It has been found that coupling system thermal hydraulic code with a flow network code is a proper way of upgrading simulation capability of DSNP to mature nuclear plant analyzer (NPA).

• 한국안전학회지
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• 제29권4호
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• pp.199-207
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• 2014

In this paper, to systematically assess the abandonment risk of main control room (MCR) fire, fire simulations with Fire Dynamics Simulator were performed and abandonment probabilities were estimated for the MCR bench-board fire of domestic reference nuclear power plant. The fire simulation scenarios performed in this study included propagating and non-propagating fires of the MCR bench-board, and the availability and unavailability of heating, ventilation, and air conditioning system (HVACS). The following results were obtained. First, temperature was the major abandonment impact factor for the MCR bench-board fire if the HVACS was available and optical density was that if the HVACS was unavailable. Second, the fire scenario contributing the MCR bench-board fire abandonment risk was identified to be only the propagating fire. Third, it was confirmed that the abandonment probability of the MCR bench-board fire for domestic reference nuclear power plant could be reduced by using the fire modeling.