• Nuclear Engineering and Technology
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• 제27권4호
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• pp.555-561
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• 1995

이 논문에서는 영광 3호기와 같이 노심내 핵계장 장치를 갖고 있는 가압형 원자력 발전소용 노심출력 분포 감시프로그램의 개발에 수정형 Borresen 모형의 응용 타당성을 검토해 보았다 이를 위해 수정형 Borresen 방정식의 소격모형해를 핵계장장치의 측정치를 경계조건으로 하여 풀었으며, 이로부터 영광 3호기 첫주기 노심의 3차원 출력분포를 계산하였다. 그 결과는 현재 영광 3호기의 축방향 출력분포 감시프로그램으로 활용되고 있는 COLSS 예측치와 비교하였으며, 이를 통하여 수정형 Borresen 모형으로 제안한 방법이 COLSS보다 축방향 출력분포를 실제에 더 가깝게 모사할 수 있음을 보였다. 노심 출력거동에 대한 예측능력이 있고 또한 전산속도면에서의 이점이 있어서 제안된 수정형 Borresen 방법이 노심출력분포 감시프로그램 개발에 유용하게 활용될 수 있다고 결론을 내렸다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 추계학술대회 논문집 전기물성,응용부문
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• pp.149-151
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• 2001

This paper presents the results of characteristics of the solid-core and suspension insulators for the reliability estimation. The various analytic techniques. such as ICP, XRD, SEM, EDS, were applied for the purpose. The alumina content of solid-core insulator was less than that of suspension insulator The cristobolite was crystallized only in solid-core insulator. The average pore size of solid-core insulator was larger than that of suspension insulator. However, the numbers of pore were fewer in the solid-core insulator.

• 대한전기학회논문지:전기기기및에너지변환시스템부문B
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• 제51권7호
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• pp.406-412
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• 2002

This paper presents a novel transformer with a new plastic magnetic core for switching power supplies. The proposed plastic magnetic core was realized using a simple manufacturing process and it can be easily designed with various shapes, suggesting that the manufacturing cost of a power transformer can be reduced using the proposed plastic magnetic core. The possible application potentials of the proposed transformer a AC/DC adaptor utilizing a transformer with the plastic magnetic core are explored. The developed adaptor, that has a maximum power of 24W, switching frequency of 125kHz, and input voltage of 110/220V, has been successfully implemented. A maximum power conversion efficiency of the experimental converter was measured at 77%, and the output was regulated at 12V within 0.2% tolerance.

• Journal of information and communication convergence engineering
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• 제21권4호
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• pp.316-321
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• 2023

In this study, we developed a conversion core that produces power by utilizing the unused magnetic field in a switchboard. The conversion core makes it possible to utilize power that is normally wasted. The conversion core is composed of a core, filter, and battery. A prototype was installed in a switchboard to conduct tests on the output, battery storage, and output boosting of multiple batteries. Energy was harvested from the magnetic field generated by a busbar of the switchboard, and the power conversion ratio of the core yielded 1.08-1.01 mW per 1 A of bus current. Supplying this technology to the market after further R&D and commercialization is expected to greatly assist in the dissemination of energy harvesting, which has not yet spread widely to the general public.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.3085-3094
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• 2022

The design concept of a Small High-flux Multipurpose LBE(Lead Bismuth Eutectic) cooled Fast Reactor (SHMLFR) was proposed in the paper. The primary cooling system of the reactor is forced circulation, and the fuel element form is arc-plate loaded high enrichment MOX fuel. The core is cylindrical with a flux trap set in the center of the core, which can be used as an irradiation channel. According to the requirements of the core physical design, a series of physical design criteria and constraints were given, and the steady and transient parameters of the reactor were calculated and analyzed. Regarding the thermal and hydraulic phenomena of the reactor, a simplified model was used to conduct a preliminary analysis of the fuel plates at special positions, and the temperature field distribution of the fuel plate with the highest power density under different coolant flow rates was simulated. The results show that the various parameters of SHMLFR meet the requirements and design criteria of the physical design of the core and the thermal design of the reactor. This implies that the conceptual design of SHMLFR is feasible.

• Nuclear Engineering and Technology
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• 제39권4호
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• pp.249-256
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• 2007

Light water reactors operated under supercritical pressure conditions have been selected as one of the promising future reactor concepts to be studied by the Generation IV International Forum. Whereas the steam cycle of such reactors can be derived from modem fossil fired power plants, the reactor itself, and in particular the reactor core, still need to be developed. Different core design concepts shall be described here to outline the strategy. A first option for near future applications is a pressurized water reactor with $380^{\circ}C$ core exit temperature, having a closed primary loop and achieving 2% pts. higher net efficiency and 24% higher specific turbine power than latest pressurized water reactors. More efficiency and turbine power can be gained from core exit temperatures around $500^{\circ}C$, which require a multi step heat up process in the core with intermediate coolant mixing, achieving up to 44% net efficiency. The paper summarizes different core and assembly design approaches which have been studied recently for such High Performance Light Water Reactors.

• Journal of information and communication convergence engineering
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• 제10권1호
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• pp.78-84
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• 2012

This paper presents a branch prediction algorithm and a 4-way set-associative cache for performance improvement of an embedded RISC core and a clock-gating algorithm with observability don’t care (ODC) operation to reduce the power consumption of the core. The branch prediction algorithm has a structure using a branch target buffer (BTB) and 4-way set associative cache that has a lower miss rate than a direct-mapped cache. Pseudo-least recently used (LRU) policy is used for reducing the number of LRU bits. The clock-gating algorithm reduces dynamic power consumption. As a result of estimation of the performance and the dynamic power, the performance of the OpenRISC core applied to the proposed architecture is improved about 29% and the dynamic power of the core with the Chartered 0.18 ${\mu}m$ technology library is reduced by 16%.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2173-2182
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• 2020

Control valves are widely used to regulate fluid flux in nuclear power plants, and there are more than 1500 control valves in the primary circuit of one nuclear power plant. With their help, the flux can be regulated to a specific level of water or steam to guarantee the energy efficiency and safety of the nuclear power plant. The flux characteristics of the control valve mainly depend on the valve core shape. In order to analyze the effects of valve core shapes on flux characteristics of control valves, this paper focuses on the valve core shapes. To begin with, numerical models of different valve core shapes are established, and results are compared with the ideal flux characteristics curve for the purpose of validation. Meanwhile, the flow fields corresponding to different valve core shapes are investigated. Moreover, relationships between the valve core opening and the outlet flux under different valve core shapes are carried out. The flux characteristics curve and equation are proposed to predict the outlet flux under different valve core openings. This work can benefit the further research of the flux control and the optimization of the valve core for control valves in nuclear power plants.

• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 2005년도 춘계학술대회 논문집
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• pp.89-92
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• 2005

Each 3D visualization program has its own different structure as for the purpose. This paper describes the design and development of an on-line 3D core data visualization program, $RocDis^{TM}$, for the nuclear simulator. It is possible to analyze the inside of the core status including neutron flux, relative power, moderator and fuel temperature in 3D distribution. Some of other essential information, axial flux distribution etc. could also display in 2D graphs. This program would be design, tuning and training for the simulator core model.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2013년도 추계학술대회
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• pp.809-812
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• 2013

본 논문은 마스터로 동작하는 32 비트 RISC 프로세서와 디지털 신호로 전력을 제어할 수 있는 다수의 슬레이브가 동기 되어 동작하는 전력 제어 임베디드 시스템을 구현한다. Core-A 플랫폼은 (주)다이나릿 시스템이 제공하는 Core-A 프로세서, AMBA 버스, SSRAM, AC97, DMA, UART, GPIO모듈 등으로 구성된다. 슬레이브는 4 비트의 디지털 데이터의 값에 비례하여 220V 전력을 제어할 수 있는 아날로그 회로와 마스터가 보내는 신호에 동기 되어 다양한 전력제어 패턴을 생성하는 제어 시스템을 설계 하였다. Core-A 플랫폼이 라이브러리로 구축된 (주)시스템센트로이드의 Flowrian2를 사용하여 소프트웨어를 크로스 컴파일하고 하드웨어 회로를 시뮬레이션으로 검증하였다. 임베디드 시스템은 FPGA 검증 보드와 CPLD 칩에 구현되었고 전력제어 아날로그 보드를 제작하여 구현하였다.