• Title/Summary/Keyword: Control rod design

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A Study on the Reaction Force Characteristics of the Gas Spring for the Automotive (자동차용 가스 스프링의 반력 특성에 관한 연구)

  • Lee, Choon Tae
    • Journal of Drive and Control
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    • v.12 no.4
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    • pp.35-40
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    • 2015
  • A gas spring provides support force for lifting, positioning, lowering, and counterbalancing weights. It offers a wide range of reaction force with a flat force characteristic, simple mounting, compact size, speed controlled damping, and cushioned end motion. The most common usage is as a support on a horizontally hinged automotive tail gate. However, its versatility and ease of use has been applied in many other industrial applications ranging from office equipment to off-road vehicles. The cylinder of a gas spring is filled with compressed nitrogen gas, which is applied with equal pressure on both sides of the piston. The surface area of the rod side of the piston is smaller than the opposite side, producing a pushing force. The magnitude of the reaction force is determined by the cross-sectional area of the piston rod and the internal pressure inside the cylinder. The reaction force is influenced by many design parameters such as initial chamber volume, diameter ratio, etc. In this paper, we investigated the reaction force characteristics and carried out parameter sensitivity analysis for the design parameters of a gas spring.

Optimal design of robot for inspection and maintenance of pressurizer in the nuclear power plant (원자력발전소 가압기 점검보수 로봇의 최적화 설계)

  • 엄재섭;정승호;김승호
    • 제어로봇시스템학회:학술대회논문집
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    • 1997.10a
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    • pp.1696-1699
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    • 1997
  • The robot mainpulator for inspection of pressurizer in the nuclear power plant has been developed, which consists of four parts : 2 arms, movable gripper, base frame, contorl console. To extract the damaged electric heating rod inside pressurizer, the gripper has been developed using wire lope and self-locking mechanism. for the examination of the structural stability of the robot manipulator, stress analysis is performed by using the ANSYS code.

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A Combination Study on the Elevation Motion Friction Compensation Parameters in Gas Spring (1) (가스 스프링 Elevation 동작 마찰력 보상 변수 조합 연구 (1))

  • Lee, Jeong-Ick
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.18 no.5
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    • pp.657-666
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    • 2017
  • In this study, factor analysis was performed to reduce the friction in the elevation motion of a stand for a 50-inchtelevision. Pipe type cross-section control was used for accurate positioning control of the piston rod. The pipe type was also compared with a labyrinth-type crosssection for the orifice. The frictional force was then reduced using gas seal lip technology. Specifications were chosen, and a volume compensation experiment was carried out using an apparatus for compensating the volume of the cylinder, which is compressed by the volume of the piston rod. Based on CAE and experimental considerations, the labyrinth-type orifice is preferred for reducing friction. For the gas seal lip technology, outer and inner diameters of ${\Phi}20$ and ${\Phi}8$ for the hollow rod were more appropriate when assuming the weight of a 50-inch television to be 30kgf. The third is that the result of total consideration in stability problem and performance of volume compensation for specification decision and volume compensation experiment is determined the final speculation of hollow rod ?8x?4 and riveting system. The last is that the labyrinth orifice is not founded that of the ${\O}0.4{\sim}0.6$ orifice both tests on 300 mm intervals.

Design and Manufacturing of Control Rod Control System for Nuclear Power System (원전 적용을 위한 제어봉 구동장치 제어시스템 설계 및 제작)

  • Lee, J.M.;Kim, C.K.;Kim, S.J.;Cheon, J.M.;Shin, J.R.;Kweon, S.M.;Nam, J.H.
    • Proceedings of the KIEE Conference
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    • 2004.07d
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    • pp.2298-2300
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    • 2004
  • This paper does with the design. implementation, and test of a CRCS for nuclear power plants. Although CRCS is still classified into non-safety class, much attention on its reliability issue has been given so far because of its importance for the stable operation of the reactor in the plant. In terms of technical aspects, our system adopts a full-duplex configuration to enhance reliability in contrast to the existing systems that are all simplex.

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$H_{\infty}$ Control of a Tracked Vehicle with ER Suspension Units (ER 현수장치를 갖는 궤도차량의 $H_{\infty}$ 제어)

  • Han, Sang-Soo;Choi, Seung-Bok
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2000.06a
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    • pp.251-256
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    • 2000
  • This paper presents dynamic modeling and controller design of a tracked vehicle installed with the double-rod type ERSU(electro-rheological suspension unit). A 16 DOF(degree-of-freedom) model for the tracked vehicle is established by Lagrangian method. After showing the spring and damping characteristics of the proposed ERSU, equivalent 2 DOF 1/12 tracked vehicle model is then formulated by regarding the spring and viscous damping coefficients under the static state as constant values. A robust LSDP(loop-shaping design procedure) $H_{\infty}$ controller compensating spring and damping parameter variations is then designed in order to suppress unwanted vibration of the vehicle. The control responses such as vertical and pitch acceleration are presented in time domain.

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Axial BP Zoning for the Soluble Boron Free Operation in Medium-Sized PWR

  • Kim, Jong-Chae;Kim, Myung-Hyun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11a
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    • pp.59-64
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    • 1996
  • Feasibility of soluble boron free operation for the medium-sized commercial reactors was investigated. Westinghouse advanced reactor, AP-600 was chosen as a design prototype. Design modification was applied for the assembly design with gadolinia burnable poison-high Gd enrichment and axial poison zoning. CASMO and NECTA-C code system checked axial offset and peaking factors as fuels burned up. A core with complex axial burnable poison zoning satisfied design goals - small excess reactivity for 18 month cycle. Therefore, critical bank positioning for three control rod banks was sought with ease. A.O. value and Fq value were kept within the safety limit.

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Conceptual Design of a Magnetic Jack Type In-Vessel Control Element Drive Mechanism (자석잭 방식 내장형 제어봉구동장치 개념설계)

  • Park, Jinseok;Lee, Myounggoo;Chang, Sanggyoon;Lee, Daehee
    • Transactions of the KSME C: Technology and Education
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    • v.3 no.3
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    • pp.225-232
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    • 2015
  • The control element drive mechanism (CEDM) is an electro-mechanical device to control reactivity of the nuclear reactor. The conventional CEDM was installed on a nozzle of the reactor vessel closure head as an ex-vessel type. However, there have been demands for an in-vessel CEDM to fundamentally eliminate the rod ejection accident. Conceptual design of the in-vessel CEDM, which was developed based on the existing technology of the ex-vessel CEDM, is introduced in this paper.

Study on the mixing performance of mixing vane grids and mixing coefficient by CFD and subchannel analysis code in a 5×5 rod bundle

  • Bin Han ;Xiaoliang Zhu;Bao-Wen Yang;Aiguo Liu;Yanyan Xi ;Lei Liu ;Shenghui Liu;Junlin Huang
    • Nuclear Engineering and Technology
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    • v.55 no.10
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    • pp.3775-3786
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    • 2023
  • Mixing Vane Grid (MVG) is one of the most important structures in fuel assembly due to its high performance in mixing the coolant and ultimately increasing Critical Heat Flux (CHF), which avoids the temperature rising suddenly of fuel rods. To evaluate the mixing performance of the MVG, a Total Diffusion Coefficient (TDC) mixing coefficient is defined in the subchannel analysis code. Conventionally, the TDC of the spacer grid is obtained from the combination of experiments and subchannel analysis. However, the processing of obtaining and determine a reasonable TDC is much challenging, it is affected by boundary conditions and MVG geometries. In is difficult to perform all the large and costing rod bundle tests. In this paper, the CFD method was applied in TDC analysis. A typical 5 × 5 MVG was simulated and validated to estimate the mixing performance of the MVG. The subchannel code was used to calculate the TDC. Firstly, the CFD method was validated from the aspect of pressure drop and lateral temperature distribution in the subchannels. Then the effect of boundary conditions including the inlet temperature, inlet velocities, heat flux ratio between hot and cold rods and the arrangement of hot and cold rods on MVG mixing and TDC were studied. The geometric effects on mixing are also carried out in this paper. The effect of vane pattern on mixing was investigated to determine which one is the best to represent the grid's mixing performance.

A Study on the Automation Equipment Development of RC Technology(I) -Equipment Design and Manufacture- (RC 기술의 자동화 장치 개발에 관한 연구(I) -장치 설계 및 제작-)

  • Kim, Ki-Joon;Kim, Sang-Jin;Song, Ja-Youn
    • Proceedings of the KIEE Conference
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    • 1994.11a
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    • pp.311-313
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    • 1994
  • RC(Rod Consolidation) technology in spent nuclear fuel management is an essential method and requires remote operation due to radiation exposure. Its technology may provide an effective means to double the storage capacity of spent fuel storage space. So development of this technology will provide a valuable contribution to establishing economical as well as technological basis for future spent fuel management.

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An automated control system for concrete temperature development in construction

  • Qiang, Sheng;Leng, Xue-jun;Wang, Xiang-rong;Zhang, Jing-tao;Hua, Xia
    • Computers and Concrete
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    • v.24 no.5
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    • pp.437-444
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    • 2019
  • PLC and its expansion module, electric ball valve and cooling pipe, electric heating steel plate and various components of the system, which is used to control test and process data. By automatically adjusting the opening of the valve, the system makes the top temperature and cooling speed develop along the ideal temperature diachronic curve. Moreover, the system enables the temperature difference between inside and surface of test block limited in a given range by automatically controlling the surface board heating. The method of physical simulation test by sandbox with built-in cooling water pipe and heating rod is adopted. On the premise of a given standard value, the operation of the system is checked under different working conditions. Further, an extension of this system is proposed, which enables its application to obtain some thermal parameters when cooperating with numerical simulation.