• Title/Summary/Keyword: vessel motions

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A Simplified Bridge-vessel Collision Model Considering with the Rotational Motions of the Vessel (선체의 회전을 고려한 선박과 교량의 간이충돌모델)

  • Lee, GyeHee
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.31 no.2A
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    • pp.43-49
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    • 2011
  • In this study, to analyze the collision behaviors of the bridge super-structure and the vessel which the collision point is located far from its rotation center such as bridge of a vessel and equipments on a barge, the simplified collision model was proposed. The model was configured to denote the mass, stiffness and the nonlinear behaviors of the bridge and the vessel. The nonlinear equation of motions of the proposed model were numerically solved by 4th order Runge-Kutta method. The parametric studies were performed for various collision conditions by the standardized Korean barge vessel in term of barge width, and its effects to the maximum collision load of bridge were analyzed.

Performance Estimation for Shipboard Directional Pedestal by Using M&S Methodologies (M&S기법을 활용한 선박용 지향성 요동보상장치 성능 분석)

  • Lee, Sungkyun;Go, Jinyong;Han, Yongsu;Kim, Changhwan
    • IEMEK Journal of Embedded Systems and Applications
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    • v.13 no.6
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    • pp.297-303
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    • 2018
  • Recently, the tasks assigned to surface ship are becoming diverse and important. In this trend, shipboard directional pedestals are widely used for surveillance and electronic warfare because ships are always under angular motion such as rolling, pitching and yawing. To estimate the performance of pedestal, the motion responses of vessel as well as mechanical characteristics of pedestal should be considered. In this study, both the motion responses of vessel which the pedestal will be mounted and the behavior of 3-axis pedestal are considered. Numerical analysis based on potential theory is used to obtained motion characteristics of vessel and then 6-DOF motions of vessel are simulated under operational condition. 1st-order time delay model and LQR control algorithm are used for modeling of pedestal drive model and control model, respectively. By using coordinate transform, the angular motions which the pedestal should compensate are calculated from the vessel's angular motion. Through these M&S methodologies, time history of pedestal behavior and maximum angular error of each pedestal axis are obtained. Overall M&S results show that 3-axis pedestal compensate the angular motion induced by vessel, efficiently.

Motion Response Characteristics of Small Fishing Vessels of Different Sizes among Regular Waves

  • DongHyup Youn;LeeChan Choi;JungHwi Kim
    • Journal of Ocean Engineering and Technology
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    • v.37 no.1
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    • pp.1-7
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    • 2023
  • The motion of small fishing vessels is significantly affected by small waves, leading to accidents, such as capsizing or sinking. This paper presents the results of two types of basin tests. The first test analyzed the characteristics of roll and pitch motions among regular waves with the same wave steepness using the drifting state of three (3G/T, 7G/T, 10G/T) small fishing vessels. The second test analyzed the motion characteristics of the 7G/T fishing vessel under different wave steepness. The first test showed that heave and roll motions are significant in the beam sea, while pitch motion is significant in the bow and stern seas. The second test shows that wave steepness has a linear relationship with roll and pitch motions in the bow and stern seas.

Study on Seismic Response Characteristics of Reactor Vessel Internals and Fuel Assembly for OBE Elimination

  • M. J. Jhung;Y. G. Yune;Lee, J. H.;Lee, J. B.
    • Nuclear Engineering and Technology
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    • v.29 no.5
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    • pp.417-431
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    • 1997
  • To resolve a general argument about OBE elimination for the future nuclear power plant design, seismic responses of reactor vessel internals and fuel assembly for Ulchin nuclear power plant units 3 and 4 in Korea are investigated as an example. Dynamic analyses of the coupled internals and core are performed for the seismic excitations using the reactor vessel motions. By investigating the response relations between OBE and SSE and their response characteristics, the critical components for OBE loading are addressed. Also the fuel assembly responses are calculated using the core plate motions and their behavior is found to be insignificant for OBE elimination.

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Study on the Seismic Analysis of the Reactor Vessel Internals (원자로내부구조물의 지진해석에 관한 연구)

  • Jhung, Myung-Jo;Park, Keun-Bae;Hwang, Won-Gul
    • Nuclear Engineering and Technology
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    • v.25 no.1
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    • pp.28-36
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    • 1993
  • Much effort is being done to standardize the PWR-type nuclear power plant in Korea. This paper presents the development of seismic design criteria for the reactor internals as a part of the standardization program for nuclear power plant. The seismic design loads of the reactor internals are calculated using the reference input motions of reactor vessel taken from Yong-gwang Nuclear Power Plant Units 3 and 4. An overview of analysis related to the basic parameters and methodologies is presented. Also, the response of internal components for the reactor vessel motions is carefully investigated.

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Development of a Stability System to prevent a Capsize of a Small Fishing Vessel (소형어선의 전복방지화 안정장치 시스템 개발에 관한 연구)

  • Cheon, Seung-Hyeon;Jeon, Ho-Hwan;Kim, Chang-Hun;Kim, Si-Yeong;,
    • Journal of Ocean Engineering and Technology
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    • v.13 no.1 s.31
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    • pp.130-137
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    • 1999
  • The wing-flap stabilizing system attached under the hull bottom of a small fishing vessel to prevent the capsize by controlling the roll motions has been developed. This paper describes the background of the system design together with the experimental results. The effectiveness of the system is proven by the towing tank tests with a 1/4 scale model, showing that the roll motions of the model are much reduced by the active flap control in multidirectional irregular waves forward speeds.

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A study on maneuvering performance improvement of a towed vessel without a power propulsion system: system modeling (견인되는 선박의 조종성능 개선에 관한 연구 : 시스템 모델링)

  • TRAN, Duc-Quan;LEE, Dong-Hun;KIM, Tae-Wan;KIM, Young-Bok;PARK, Hwan-Cheol
    • Journal of the Korean Society of Fisheries and Ocean Technology
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    • v.54 no.4
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    • pp.343-352
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    • 2018
  • In this study, a motion control problem for the vessels towed by tugboats or towing ships on the sea is considered. The towed vessel looks like the barge ship, which is used for many purposes. In these vessels, basically, the power propulsion system is not installed but just towed by a towing vessel such as tugboats with ropes and wires. It means that the motions of towed vessel are basically dependent on the tracking route of towing boat. Therefore, in some cases, undesirable and unpredictable motions may be made by environmental factors such as wave, wind attack and so on. As a result, a collision accident with others may occur during maneuvering situation. Based on these facts, the authors try to encourage the steering performance of the towed vessel by using controllable rudders without any propulsion system. In this study, especially, a controllable vessel with three rudders is considered, and a mathematical model is induced for the future study. The model is described as surge, sway motion and inertia moment by following the general representation method for the surface ship.

The Effect of Seismic Level Increase on the Reactor Vessel Internals and Fuel Assemblies for the Korean Standard Suclear Power Plant (지진레벨의 증가가 한국표준형 원자력발전소의 원자로 내부구조물 및 핵연 료 집합체에 미치는 영향)

  • Jhung, M. J.
    • Journal of KSNVE
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    • v.7 no.1
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    • pp.33-41
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    • 1997
  • To cover a range of possible site conditions where the Korean standard nuclear power plant may be constructed, a range of generic site conditions is selected for geologic and seismologic evaluation. To envelop other Asian countries as well as the Korean peninsula, there is an attempt to increase the seismic level to 0.3g ground motions for the safe shutdown earthquake. The dynamic analyses of the reactor vessel internals and fuel assemblies are performed for the increased motions and the effect of seismic level on the response is investigated. Also the nonlinear response characteristics are discussed by comparing the loads between operating basis earthquake and safe shutdown earthquake excitations. The design adequacy of the reactor vessel internals and fuel assemblies for the increased seismic level is addressed.

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Generation Method of Spatiotemporal Image for Detecting Leukocyte Motions in a Microvessel (미소혈관내 백혈구 운동검출을 위한 시공간 영상 생성법)

  • Kim, Eung Kyeu
    • Journal of the Institute of Electronics and Information Engineers
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    • v.53 no.9
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    • pp.99-109
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    • 2016
  • This paper presents a method for generating spatiotemporal images to detect the leukocyte motions in a microvessel. By using the constraint that the leukocytes move along the contour line of a blood vessel wall, the method detects leukocyte motions and then generates spatiotemporal images. the translational motion by a movement in vivo is removed first by the template matching method. Next, a blood vessel region is detected by the automatic threshold selection method to binarize the temporal variance image, then a blood vessel wall's contour is expressed by B-spline function. With the detected blood vessel wall's contour as an initial curve, the plasma layer of the best accurate position is determined to be the spatial axis by snake. Finally, the spatiotemporal images are generated. The experimental results show the spatiotemporal images are generated effectively through the comparison of each step of three image sequences.

Modelling of RV Ledge Region for Dynamic Analysis of Coupled Reactor Vessel Internals and Core

  • Jhung, Myung J.
    • Nuclear Engineering and Technology
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    • v.30 no.2
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    • pp.164-172
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    • 1998
  • This paper presents the detailed modelling of reactor vessel ledge region for the dynamic analysis of the coupled internals and core model. The dynamic responses due to earthquake and pipe break are calculated using the input motions of reactor vessel taken from Ulchin nuclear power plant units 3 and 4. Two different representations for detailed and simplified models of the RV ledge region are made. The dynamic responses of the reactor internals components are compared between them. Response characteristics are reported and simplified model is suggested for earthquake and pipe break analysis for the future design of the reactor internals.

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