• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1991년도 한국자동제어학술회의논문집(국내학술편); KOEX, Seoul; 22-24 Oct. 1991
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• pp.900-904
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• 1991

It is important and difficult to control the steam temperature in the once through boiler. Generally, steam temperature of once through boiler not only is controlled by boiler spray water flow, but also is influenced by feed water flow and fuel flow. So we have to make the same gain of fuel flow controller and feed water flow controller. This paper is shown the design and test of steam temperature and feed water flow control system for once through boiler in pusan thermal power plant.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1987년도 한국자동제어학술회의논문집; 한국과학기술대학, 충남; 16-17 Oct. 1987
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• pp.625-630
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• 1987

Technology associated with power plant control system has been heavily rely on foreign technology. The main reason is that the system has tomaintain stringent reliability and stability. Localization of this system can be started from localization of modules necessary for maintenance and repair in hydraulic and thermal power plant. Gradually and eventually system engineering capability can be built up to design and develop nuclear power plant control system through technology accumulation. Methods are presented to achieve this goal.

• Nuclear Engineering and Technology
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• 제31권4호
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• pp.391-400
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• 1999

A conceptual core design of the 1,300MWe KNGR (Korean Next Generation Reactor) without using soluble boron for reactivity control was developed to determine whether it is technically feasible to implement SBF (Soluble Boron Free) operation. Based on the borated KNGR core design, the fuel assembly and control rod configuration were modified for extensive use of burnable poison rods and control rods. A new fuel rod, in which Pu-238 had been substituted for a small amount of U-238 in fuel composition, was introduced to assist the reactivity control by burnable poison rods. Since Pu-238 has a considerably large thermal neutron capture cross section, the new fuel assembly showed good reactivity suppression capability throughout the entire cycle turnup, especially at BOC (Beginning of Cycle). Moreover, relatively uniform control of power distribution was possible since the new fuel assemblies were loaded throughout the core. In this study, core excess reactivity was limited to 2.0 %$\delta$$\rho$ for the minimal use of control rods. The analysis results of the SBF KNGR core showed that axial power distribution control can be achieved by using the simplest zoning scheme of the fuel assembly Furthermore, the sufficient shutdown margin and the stability against axial xenon oscillations were secured in this SBF core. It is, therefore, concluded that a SBF operation is technically feasible for a large sized LWR (Light Water Reactor).

• Nuclear Engineering and Technology
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• 제51권7호
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• pp.1721-1728
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• 2019

The advanced node core code CORCA-3D is one of the independent developed codes of NPIC for the nuclear reactor core design. CORCA-3D code can calculate the few-group cross section, solve the 3D diffusion equations, consider the thermal-hydraulic feedback, reconstruct the pin-by-pin power. It has lots of functions such as changing core status calculation, critical searching, control rod value calculation, coefficient calculation and so on. The main theory and functions of CORCA-3D code are introduced and validated with a lot of reactor measured data and the SCIENCE system. Now, CORCA-3D code has been applied in ACP type reactor nuclear cores design.

• 생물환경조절학회지
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• 제27권4호
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• pp.294-301
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• 2018

겨울철에 열손실을 줄이기 위해 많은 온실에서 보온커튼을 사용하고 있다. 그러나 적절한 보온커튼을 선택할 때 판단 자료로 활용할 수 있는 명확한 기준이 없는 실정이며 이를 위해서는 보온재의 보온 특성에 대한 정량적인 값이 필요하다. 본 연구에서는 BES를 사용하여 보온커튼의 관류열전달계수를 산정하는 시뮬레이션 모델을 개발하였다. 일중 및 이중 PE필름 피복에 대한 관류열전달계수의 실험값을 사용하여 시뮬레이션 결과를 검증하였다. 검증된 모델을 사용하여 문헌에서 제시된 각종 열적 특성을 가진 보온커튼에 대한 관류열전달계수를 산정하고 비교분석하였다. 개발된 시뮬레이션 모델은 다양한 보온커튼의 관류열전달계수를 산정하는 데 활용될 수 있을 것이며, 제시된 관류열전달계수는 보온커튼의 성능을 정량적으로 비교하는데 유용하게 활용될 수 있을 것으로 판단된다.

• 한국항공우주학회지
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• 제39권1호
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• pp.76-83
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• 2011

본 논문에서는 초고주파 탐색기 신호처리부의 방열설계 과정을 연구하였다. 신호처리부는 고온환경조건과 초기고장배제시험 조건을 고려하여 설계되어져야 한다. 우선, 신호처리부의 열적 신뢰성 검증을 위하여 전산 열해석을 수행하였으며, 해석 결과를 바탕으로 열적으로 취약한 소자에 방열 블록을 적용하였다. 이 기술은 방열블록이 각각의 소자의 열 부하를 조절하기 때문에 효율적인 방열을 할 수 있게 된다. 다음으로 전산모델 결과와 실험 결과를 검증하였으며, 이를 통하여 신호처리부의 열적 신뢰성을 확인하였다. 또한 실험결과와 해석결과의 최대 온도차가 약 $2^{\circ}C$ 임을 알 수 있다.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.19-26
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• 2020

Small nuclear reactor features higher power capacity, longer operation life than conventional power sources. It could be an ideal alternative of existing power source applied for special equipment for terrestrial or underwater missions. In this paper, a 25kWe heat pipe cooled reactor power source applied for multiple use is preliminary designed. Based on the design, a thermal-hydraulic analysis code for heat pipe cooled reactor is developed to analyze steady and transient performance of the designed nuclear reactor. For reactor design, UN fuel with 65% enrichment and potassium heat pipes are adopted in the reactor core. Tungsten and LiH are adopted as radiation shield on both sides of the reactor core. The reactor is controlled by 6 control drums with B₄C neutron absorbers. Thermoelectric generator (TEG) converts fission heat into electricity. Cooling water removes waste heat out of the reactor. The thermal-hydraulic characteristics of heat pipes are simulated using thermal resistance network method. Thermal parameters of steady and transient conditions, such as the temperature distribution of every key components are obtained. Then the postulated reactor accidents for heat pipe cooled reactor, including power variation, single heat pipe failure and cooling channel blockage, are analyzed and evaluated. Results show that all the designed parameters satisfy the safety requirements. This work could provide reference to the design and application of the heat pipe cooled nuclear power source.

• 설비공학논문집
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• 제17권3호
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• pp.243-249
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• 2005

The present study has been conducted to simulate dynamics of a gas engine-driven heat pump(GHP) for design of control algorithm. The dynamic modeling of a GHP was based on conservation laws of mass and energy. For automatic control of refrigerant pressures, actuators such as engine speed, outdoor fan, coolant three-way valves and liquid injection valve were PI or P controlled. The simulation results showed physical behavior that is realistic enough to apply for control algorithm design.

• 한국항공우주학회지
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• 제42권12호
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• pp.1013-1019
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• 2014

저궤도 관측위성에 탑재된 영상처리장치의 온도제어를 위하여 사용하는 열적완충질량을 대체할 수 있는 상변화물질의 성능에 대하여 수치해석적으로 분석하였다. 관측위성에 사용되는 고정밀 영상처리장치는 임무에 따라 주기적으로 작동하며 발열량이 매우 큰 반면, 온도에 민감하여 작동허용 온도범위가 매우 좁다. 이러한 장치의 온도를 제어하기 위하여 국산 저궤도 관측위성에서는 열적완충질량을 이용하여 부품의 온도변화 시상수를 증가시키는 효율적인 설계를 적용하였지만, 질량이 증가하는 단점이 있다. 본 연구에서는 질량을 최소화하며 부품 온도를 안정적으로 유지할 수 있도록 고상-액상 상변화물질을 이용한 열제어 장치를 제안하였으며, 수치해석을 통하여 열적 완충질량에 대한 유효성을 비교/검증하였다. 상변화물질을 이용한 열제어 장치는 열적완충질량을 대체하여 효과적인 온도제어가 가능할 뿐 아니라 질량도 열적완충질량의 약 12% 정도로 감소시킬 수 있었다.

• 한국연소학회:학술대회논문집
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• 한국연소학회 2014년도 제49회 KOSCO SYMPOSIUM 초록집
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• pp.19-20
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• 2014

Boiler design should be desinged to maximize thermal efficiency of the system under imposed load requirement and a boiler should be validated for transient operation. If a proper prediction is possible on the transient behavior and transient characteristics of a boiler, one may asses the performance of boiler component, control logics and operation procedures. In this work, dynamic modeling method of boiler is presented and dynamic simulation of load runback scenario was carried out on suprecritical oil-firing boiler.