• Proceedings of the Korean Society of Precision Engineering Conference
• /
• 2008.06a
• /
• pp.281-282
• /
• 2008

• Proceedings of the Korean Society for Emotion and Sensibility Conference
• /
• 2011.11a
• /
• pp.13-14
• /
• 2011

• Proceedings of the Korean Institute of Intelligent Systems Conference
• /
• 2000.05a
• /
• pp.51-54
• /
• 2000

In variable structure control algorithm, sliding mode makes the closed loop system insensitive to modelling uncertainties and external disturbances. However due to imperfections in switching, the system trajectory chatters, which is very undesirable. And the insensitivity property of a sliding mode controller is present only when the system is in the sliding mode. To overcome these shortcomings, in this paper, new sliding mode control algorithm using time-varying sliding surface and fuzzy PI structrue is proposed.

• Journal of Environmental Science International
• /
• v.13 no.2
• /
• pp.129-134
• /
• 2004

Understanding aspects of the use of Korean representative Soraksan National Park and investigating the factors affecting visitors' decision-making, this study aims to suggest a positive development plan for the rational use of the national park. The questionnaire is for those who have visited Soraksan National Park more than once. This research shows that most of the visitors wish ‘entrance congestion’ to be solved by introducing a ‘previous reservation’ system and a non-polluting shuttle bus; therefore there is a chance that they could be introduced for the settlement of the existing problems.

• Proceedings of the Korean Society of Coastal and Ocean Engineers Conference
• /
• 2001.08a
• /
• pp.102-107
• /
• 2001

• Proceedings of the Korean Society of Precision Engineering Conference
• /
• 2010.11a
• /
• pp.719-720
• /
• 2010

• Proceedings of the KSRS Conference
• /
• 2004.10a
• /
• pp.562-563
• /
• 2004

Environmental management system has been constructed using by marine GIS, which is applied latest scientific algorithm, and fisheries related data for the citizens of the Jinhae Bay and executive officers. Through this system, we will get more easily marine environmental data, and production features of aquaculture farming areas.

• Proceedings of the KIEE Conference
• /
• 2002.11c
• /
• pp.546-549
• /
• 2002

In this paper, a simulation system, which is almost same with the real motor-mechanical control system, is established. The real system is identified by using the data from DSP(TMS320F240). The RLS(Recursive Least Square) algorithm is used for the identification and MATLAB Simulink program is used for simulation. The exact simulation system obtained by using the proposed method is very useful for analysis and design of motor-mechanical control systems.

• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.10a
• /
• pp.1073-1074
• /
• 2005

• Nuclear Engineering and Technology
• /
• v.28 no.5
• /
• pp.440-451
• /
• 1996

With emphasis on safety, this study addresses for better design condition for the cooling system in a wet-type interim spent fuel storage facility, using a probabilistic safety assessment method. To incorporate the design renovation into the design phase, a simple approach is proposed. By taking the cooling system of a reference design, a fault tree analysis was performed to identify the weak point of the considered system, and then basic factors for design renovation were defined. A total of 21 design alternatives were selected through the combination of the basic factors. Finally, the optimum design alternative for the cooling system is derived by means of the cost and effect analysis based on the estimated cost, system reliability and assumed probabilistic safety criteria. With the assumption that the failure frequency of at-reactor spent fuel cooling system compiles with probabilistic safety criteria for the interim spent fuel cooling system, it was shown that the optimum alternative should have l00% cooling loop redundancy with one pump per cooling loop and a cleanup system installed separately from the main loop. Furthermore, it also should be classified into safety system. The result of this study can be used as a useful basis to identify factors of safety concern and to establish design requirements in the future. The method also can be applied for other nuclear facilities.