• 제어로봇시스템학회:학술대회논문집
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• 1989.10a
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• pp.230-234
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• 1989

This paper presents the design of a prototype robot and architecture of a distributed control system. The robot, named as KAEROT, has been developed for the purpose of the reduction of personal radiation exposure and the remote maintenance tasks in nuclear facilities. The mobile system with robotic manipulator has been designed to go up and down stairs. For the dextrous handling, this manipulator will be designed as a redundant type to act like a human arm. Manipulator control system is to be extended easily for further usage with a modular architecture to get independency and reliability by minimizing EMI effects.

• 제어로봇시스템학회:학술대회논문집
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• 1990.10a
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• pp.731-735
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• 1990

The mobile robot, named as KAEROT, is designed to go up and down stairs in nuclear facilities. To get a proper stable motion, kinematic modeling and analysis are seriously considered and new climbing algorithm is proposed focused on the stability. A couple of small wheels of one planetary wheel have to contact the surface ol stairs all the time to give the guarantee for stability and safety. To confirm the validity of the proposed algorithm, simulation is carried out. The results make evident of feasibility for the algorithm.

• Journal of Soil and Groundwater Environment
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• v.22 no.3
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• pp.1-9
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• 2017

The numerical analysis of groundwater flow is indispensable for predicting problems associated with water resource development, civil works, environmental hazards, and nuclear power plant construction. Korea lacks public regulatory procedures and guidelines for groundwater flow modeling, especially in nuclear facility sites, which makes adequate evaluation difficult. Feasible step-by-step guidelines are also unavailable. Consequently, reports on groundwater flow modeling have low-grade quality and often present controversial opinions. Additionally, without public guidelines, maintaining consistency in reviewing reports and enforcing laws is more challenging. In this study, the guidelines for groundwater flow modeling were reviewed for three countries - the United States (Documenting Groundwater Modeling at Sites Contaminated with Radioactive Substances), Canada (Guidelines for Groundwater Modelling to Assess Impacts of Proposed Natural Resource Development Activities), and Australia (Australian Groundwater Modelling Guidelines), with the aim of developing groundwater flow modeling regulatory guidelines that can be applied to nuclear facilities in Korea, in accordance with the Groundwater Act, Environmental Impact Assessment Act, and the Nuclear Safety Act.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2015.05a
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• pp.264-266
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• 2015

Currently as cyber threats grow up targeting nuclear power plants(NPP), licensees must guarantee that computer and information systems of nuclear facilities can be adequately protected against cyber attack. Especially critical system that cause illegal transfer of nuclear material and adverse impact to public safety need protecting. In this paper, we surveying the cyber threat examples targeted at NPP, and taxonomy the method of cyber security for NPPs in korea through analyzing the methodology to identify critical system and address cyber security controls for nuclear facilities.

• Nuclear Engineering and Technology
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• v.41 no.5
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• pp.739-746
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• 2009

This paper introduces facility operation modeling and simulation based primarily on a discrete event system modeling scheme. Many modern industrial facilities are so complex that their operational status cannot be estimated by simple calculations. In general, a facility can consist of many processes and transfers of material between processes that may be modeled as a discrete event system. This paper introduces the current status of studies on operation modeling and simulation for typical nuclear facilities, along with some examples. In addition, this paper provides insights about how a discrete event system can be applied to a model for a nuclear facility. A headend facility is chosen for operation modeling and the simulation, and detailed procedure is thoroughly described from modeling to an analysis of discrete event results. These kinds of modeling and simulation are very important because they can contribute to facility design and operation in terms of prediction of system behavior, quantification of facility capacity, bottleneck identification and efficient operation scheduling.

• Nuclear Engineering and Technology
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• v.41 no.10
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• pp.1235-1242
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• 2009

Probabilistic seismic hazard analysis (PSHA) is routinely conducted in the US for nuclear plants, for the determination of appropriate seismic design levels. These analyses incorporate uncertainties in earthquake characteristics in stable continental regions (where direct observations of large earthquakes are rare), in estimates of rock motions, in site effects on strong shaking, and in the damage potential of seismic shaking for engineered facilities. Performance goals related to the inelastic deformation of individual components, and related to overall seismic core damage frequency, are used to determine design levels. PSHA has the ability to quantify and document the important uncertainties that affect seismic design levels, and future work can be guided toward reducing those uncertainties.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.226.1-226
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.351.2-351
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.320.2-320
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.283.1-283
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• 2002