• 대한전자공학회:학술대회논문집
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• 대한전자공학회 2003년도 컴퓨터소사이어티 추계학술대회논문집
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• pp.167-170
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• 2003

In this paper, a design and experiment of PCI Express Core verification Model is described. The model targeting Endpoint core verification is designed by using newly-emerging SystemC which is a system design language based on a new C++ class library and simulation engine. In the verification model, we developed a SystemC Host System model which act as a Root Complex and Device Driver dedicated to the PCI Express Endpoint RTL Core. The test of Host System Model is guided by scenarios which implements and acts point of Device Driver and Root Complex and shows the result of simulation. Also, We present the full structure of verification model and Host model.

• 안보군사학연구
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• 통권3호
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• pp.243-263
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• 2005

The purpose of present study is to applied center assess method to Military General's Promotion System. This study aim to examine assessment center method based on core competency model will be applied to Military General's Promotion System and Human Resource Management. This study propose that Military General's core competency model based on job analysis to identify competency of Army, Navy, Air Force's Generals and to identify the consequences and performances of assess center method. This study propose that assess center method applied to Military General's Promotion System have many kinds. Facilitated Simulation methods were Planning and Analysis /Oral Presentation, Presentation management Coaching, customer /Peer lnteraction. Non-facilitated Simulation methods were In-Basket game, Leaderless Group Discussion, role playing. And this study propose that Military General's assessment center method based on core competency model will be effective in Military field.

• 한국초전도저온공학회:학술대회논문집
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• 한국초전도저온공학회 2003년도 추계학술대회 논문집
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• pp.243-245
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• 2003

The method to fabricate the cryostat of superconducting cable is extrusion type which is used Aluminum ingot under high temperature such as 45$0^{\circ}C$ and the cryostat is formed above cable core and MLI layer. In this case, it is expected to occur thermal injury in cable core and MLI layer, so it is necessary to study to prevent thermal injury. So in this paper, using simulation on radiation and convection which are accompany with fabricating cryostat, it is suggested to reduce the thermal injury. By measuring simulation temperature and real temperature, it is possible to check the temperature on cable core and MLI layer and using these temperature, it is possible to predict whether thermal injury is occurred or not on cable core and MLI layer.

• 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.

• 한국간호교육학회지
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• 제20권1호
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• pp.37-46
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• 2014

Purpose: This study was to measure and identify the differences of perceived confidence in practice of core basic nursing skills performed by new graduate nurses in Korea. Methods: The tool used in this study was a questionnaire for measuring the confidence in 20 items of core basic nursing skills which was structured based on Korean Accreditation Board of Nursing Education tool. 231 new graduate nurses participated in this study. The reliability of this questionnaire had Cronbach's ${\alpha}$ .918. Results: Subjects who experienced simulation education and standard patient education were 86.6% and 35.9%, respectively. Item enema intervention, tracheostomy care, and blood transfusion showed low practice confidence level. These items showed significant differences on whether the subjects experienced simulation and clinical practicum or not. Conclusion: Developing and managing clinical education program under deep cooperation between practicum agency and clinical instructor are needed. Simulation practicum will complement insufficient core basic nursing skills between newly graduated nurses before they allocate at the clinical department.

• 한국자동차공학회논문집
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• 제21권5호
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• pp.82-86
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• 2013

The automotive weather strip has the functions isolating of dust, water, noise and vibration from outside. The core of weather strip is made of steel with stiffness. By using the wire formed as the core of weather strip, weight can be reduced as much as 35% by comparing with existing steel core. For this reason, forming wire is necessary to keep the zigzag shape as it is. The deformation which is occurred during forming process can be predicted and it can be used in case of manufacturing dies through CAE. In this paper, rolling process conditions are deduced and the springback amount is predicted after rolling process by using the simulation. The springback amount of product is measured by using optical microscope, and measurement result is compared with the simulation result of springback as the same condition. The suitable gap between dies to compensate springback after rolling process is predicted through simulation and it is used for manufacturing dies.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.764-769
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• 2022

The United Arab Emirates is currently building and operating four units of the APR-1400 developed by a South Korean vendor, Korea Electric Power Corporation (KEPCO). This paper attempts to perform APR-1400 reactor core analysis by using the well-known two-step method. The two-step method was applied to the APR-1400 first cycle using the open-source nodal diffusion code, KOMODO. In this study, the group constants were generated using CASMO-4 fuel transport lattice code. The simulation was performed in Hot Zero Power (HZP) at steady-state and transient conditions. Some typical parameters necessary for the Nuclear Design Report (NDR) were evaluated in this paper, such as effective neutron multiplication factor, control rod worth, and critical boron concentration for steady-state analysis. Other parameters such as reactivity insertion, power, and fuel temperature changes during the Reactivity Insertion Accident (RIA) simulation were evaluated as well. The results from KOMODO were verified using PARCS and SIMULATE-3 nodal core simulators. It was found that KOMODO gives an excellent agreement.

• 정보과학회지
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• 제25권11호
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• pp.45-50
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• 2007

• Journal of Communications and Networks
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• 제7권3호
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• pp.377-384
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• 2005

The purpose of this research is to develop and evaluate a traffic engineering architecture that uses local state information. This architecture is applied to an Internet protocol radio access network (RAN) that uses multi-protocol label switching (MPLS) and differentiated services to support mobile hosts. We assume mobility support is provided by a protocol such as the hierarchical mobile Internet protocol. The traffic engineering architecture is router based-meaning that routers on the edges of the network make the decisions onto which paths to place admitted traffic. We propose an algorithm that supports the architecture and uses local network state in order to function. The goal of the architecture is to provide an inexpensive and fast method to reduce network congestion while increasing the quality of service (QoS) level when compared to traditional routing and traffic engineering techniques. We use a number of different mobility scenarios and a mix of different types of traffic to evaluate our architecture and algorithm. We use the network simulator ns-2 as the core of our simulation environment. Around this core we built a system of pre-simulation, during simulation, and post-processing software that enabled us to simulate our traffic engineering architecture with only very minimal changes to the core ns-2 software. Our simulation environment supports a number of different mobility scenarios and a mix of different types of traffic to evaluate our architecture and algorithm.

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1916-1938
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• 2019

The objective of this paper is to discuss the modeling principles of phenomena governing core degradation/melting and in-vessel melt relocation during severe accidents in light water reactors. The proposed modeling approach has been applied in the development of a new accident simulation package, COMPASS (COre Meltdown Progression Accident Simulation Software). COMPASS can be used either as a stand-alone tool to simulate in-vessel meltdown progression up to and including RPV failure, or as a component of an integrated simulation package being developed in Korea for the APR1400 reactor. Interestingly, since the emphasis in the development of COMPASS modeling framework has been on capturing generic mechanistic aspects of accident progression in light water reactors, several parts of the overall model should be useful for future accident studies of other reactor designs, both PWRs and BWRs. The issues discussed in the paper include the overall structure of the model, the rationale behind the formulation of the governing equations and the associated simplifying assumptions, as well as the methodology used to verify both the physical and numerical consistencies of the overall solver. Furthermore, the results of COMPASS validation against two experimental data sets (CORA and PHEBUS) are shown, as well as of the predicted accident progression at TMI-2 reactor.