• Title/Summary/Keyword: Control rod design

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Development and validation of reactor nuclear design code CORCA-3D

  • An, Ping;Ma, Yongqiang;Xiao, Peng;Guo, Fengchen;Lu, Wei;Chai, Xiaoming
    • Nuclear Engineering and Technology
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    • v.51 no.7
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    • pp.1721-1728
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    • 2019
  • The advanced node core code CORCA-3D is one of the independent developed codes of NPIC for the nuclear reactor core design. CORCA-3D code can calculate the few-group cross section, solve the 3D diffusion equations, consider the thermal-hydraulic feedback, reconstruct the pin-by-pin power. It has lots of functions such as changing core status calculation, critical searching, control rod value calculation, coefficient calculation and so on. The main theory and functions of CORCA-3D code are introduced and validated with a lot of reactor measured data and the SCIENCE system. Now, CORCA-3D code has been applied in ACP type reactor nuclear cores design.

Vibration from a Shaft-Bearing-Plate System Due to an Axial Excitation of Helical Gears

  • Park, Chan-Il
    • Journal of Mechanical Science and Technology
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    • v.20 no.12
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    • pp.2105-2114
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    • 2006
  • In this paper, a simplified model is studied to predict analytically the vibration from the helical gear system due to an axial excitation of helical gears. The simplified model describes gear, shaft, bearing, and housing. In order to obtain the axial force of helical gears, the mesh stiffness is calculated in the load deflection relation. The axial force is obtained from the solution of the equation of motion, using the mesh stiffness. It is used as a longitudinal excitation of the shaft, which in turn drives the gear housing through the bearing. In this study, the shaft is modeled as a rod, while the bearing is modeled as a parallel spring and damper only supporting longitudinal forces. The gear housing is modeled as a clamped circular plate with viscous damping. For the modeling of this system, transfer matrices for the rod and bearing are used, using a spectral method with four pole parameters. The model is validated by finite element analysis. Using the model, parameter studies are carried out. As a result, the linearized dynamic shaft force due to the gear excitation in the frequency domain was proposed. Out-of-plan displacement from the forced vibrating circular plate and the renewed mode normalization constant of the circular plate were also proposed. In order to control the axial vibration of the helical gear system, the plate was more important than the shaft and the bearing. Finally, the effect of the dominant design parameters for the gear system can be investigated by this model.

Design of FPGA Logic for Control Rod Control System Power Controller (제어봉 구동장치 제어시스템 전력제어기용 FPGA 설계)

  • Lee, Jong-Moo;Shin, Jong-Ryeol;Kwon, Soon-Man;Park, Min-Kook;Kim, Choon-Kyong;Cheon, Jong-Min
    • Proceedings of the KIEE Conference
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    • 2004.07d
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    • pp.2295-2297
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    • 2004
  • 원자로의 제어봉 구동장치에 공급되는 전력을 제어하는 전력함 전력제어기는 DSP를 이용하여 디지털 시스템으로 설계하였다. 전력제어기는 Master/Slave 형태로 이중화되어 신뢰성이 향상시켰고 전력제어기의 CPU 보드에는 제어용과 통신용 두 개의 DSP를 사용하여 전력제어기의 주 기능인 제어/감시와 통신 기능을 분리하여 담당시켰다. 전력제어기에 요구되는 이러한 기능들을 효과적으로 수행하도록 CPU 보드에 디지털 논리구현 장치인 FPGA를 설치하여 메모리 주소 및 각 부품의 칩 선택 신호를 생성, 이중화 전력제어기 상호간 신호 수수, 각종 고장 검출 및 점호각 신호 발생 등의 역할을 하도록 하였다.

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Morphology-dependent Nanocatalysis: Rod-shaped Oxides

  • Shen, Wenjie
    • Proceedings of the Korean Vacuum Society Conference
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    • 2013.02a
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    • pp.130-131
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    • 2013
  • Nanostructured oxides are widely used in heterogeneous catalysis where their catalytic properties are closely associated with the size and morphology at nanometer level. The effect of particle size has been well decumented in the past two decades, but the shape of the nanoparticles has rarely been concerned. Here we illustrate that the redox and acidic-basic properties of oxides are largely dependent on their shapes by taking $Co_3O_4$, $Fe_2O_3$, $CeO_2$ and $La_2O_3$ nanorods as typical examples. The catalytic activities of these rod-shaped oxides are mainly governed by the nature of the exposed crystal planes. For instance, the predominant presence of {110} planes which are rich in active $Co^{3+}$ on $Co_3O_4$ nanorods led to a much higher activity for CO oxidation than the nanoparticles that mainly exposed the {111} planes. The simultaneous exposure of iron and oxygen ions on the surface of $Fe_2O_3$ nanorods have significantly enhanced the adsorption and activation of NO and thereby promoted the efficiency of DeNOx process. Moreover, the exposed surface planes of these rod-shaped oxides mediated the reaction performance of the integrated metal-oxide catalysts. Au/$CeO_2$ catalysts exhibited outstanding stability under water-gas shift conditions owing to the strong bonding of gold particle on the $CeO_2$ nanorods where the formed gold-ceria interface was resistant towards sintering. Cu nanoparticles dispersed on $La_2O_3$ nanorods efficiently catalyzed transfer dehydrogenation of primary aliphatic alcohols based on the uniue role of the exposed {110} planes on the support. Morphology control at nanometer level allows preferential exposure of the catalytically active sites, providing a new stragegy for the design of highly efficient nanostructured catalysts.

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Experimental investigation on multi-mode vortex-induced vibration control of stay cable installed with pounding tuned mass dampers

  • Liu, Min;Yang, Wenhan;Chen, Wenli;Li, Hui
    • Smart Structures and Systems
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    • v.23 no.6
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    • pp.579-587
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    • 2019
  • In this paper, pounding tuned mass dampers (PTMDs) were designed to mitigate the multi-mode vortex-induced vibration (VIV) of stay cable utilizing the viscous-elastic material's energy-dissipated ability. The PTMD device consists of a cantilever metal rod beam, a metal mass block and a specially designed damping element covered with viscous-elastic material layer. Wind-tunnel experiment on VIV of stay cable model was set up to validate the effectiveness of the PTMD on multi-mode VIV mitigation of stay cable. By analyzing and comparing testing results of all testing cases, it could be verified that the PTMD with viscous-elastic pounding boundary can obviously mitigate the VIV amplitude of the stay cable. Moreover, the installed location and the design parameters of the PTMD device based on the controlled modes of the primary stay cable, would have a certain extent suppression on the other modal vibration of the stay cable, which means that the designed PTMDs are effective among a large band of frequency for the multi-mode VIV control of the stay cable.

Development of A Control Rod Control System for Nuclear Power Plants (제어봉 구동장치 제어시스템용 전력함 개발)

  • Lee, J,M.;Kim, C.K.;Kim, S.J.;Cheon, J.M.;Park, M.K.;Jung, S.H.;Nam, J.H.
    • Proceedings of the KIEE Conference
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    • 2003.07d
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    • pp.2274-2276
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    • 2003
  • This paper deals 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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A Study on the Characteristics of Zr-4 End Cap Welded Joints Using Resistance Upset Welding (저항업셋 용접법을 이용한 Zr-4 End Cap용접부의 특성에 관한 연구)

  • 박철주;김형수;이영호;강원석
    • Journal of Welding and Joining
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    • v.10 no.4
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    • pp.240-249
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    • 1992
  • The objective of this study is to investigate the characteristics of welded joints on the Zircaloy-4 resistance upset welding for HWR(Heavy Water reactor)fuel rods. To estimate the characteristics of welded joints, the various tests were performed on the test coupons systematically with a wide range of each welding parameters in terms of a tensile test, burst test, knoop hardness test and metallography. Major results obtained in this study are as follows: 1. The tube and machined with 120.deg. projection was the reliable weld joint design for the nuclear fuel rod end cap welding. 2. As the weld current and the amount of upset increased linearly with increasing welding main heat input, it could make an estimate of their variation in accordance with the phase shift control. 3. It was found that an increase in squeeze force has an effect on the upset contour of welded joint because the amount of upset were increased by the change of squeeze force.

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Feasibility Study on the Utilization of Mixed Oxide Fuel in Korean 900MWe PWR Core Through Conceptual Core Nuclear Design and Analysis

  • Joo, Hyung-Kook;Kim, Young-Jin;Jung, Hyung-Guk;Sohn, Dong-Seong
    • Nuclear Engineering and Technology
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    • v.29 no.4
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    • pp.299-309
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    • 1997
  • The neutronic feasibility of typical Korean three-loop 900MWe class PWR core loaded with mixed oxide fuels for both annual and 18-month cycle strategies has been investigated as a means for spent fuel management. For this study, a method of determining equivalent plutonium content was developed under the equivalence concept which gives the same cycle length as uranium fuel. Optimal plutonium zoning within the MOX assembly was also designed with the aim of minimizing the peak md power. Conceptual core designs hate hen developed for equilibrium cycle with the following variations: annual and 18-month cycle, 1/3 and full MOX loading schemes, and typical and high moderation lattice. The analysis of key core physics parameters shows that in all cases considered satisfactory core designs seem to be feasible, though addition of control rod system and change in Technical Specification for soluble boron concentration are required for full MOX loading in order to meet the current design requirements.

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Design of Optimal Locating Point of the Hydraulic Cylinder Actuating a Roller-Link Type Rotating Floodgate (콤플렉스법에 의한 롤러-링크 부착형 전도수문 구동용 유압실린더의 최적 설치점 설계)

  • Lee, S.R.
    • Journal of Drive and Control
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    • v.9 no.3
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    • pp.29-36
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    • 2012
  • The hydraulic cylinder is used for actuating the roller-link type rotating floodgate which controls the volume of water in the reservoir. The locating points of hydraulic cylinder are restricted to the limited space and determined to minimize the cylinder force necessary for actuating the floodgate. Generally, the head end point of cylinder is fixed at underground and the rod end point of cylinder is connected to the support link. Therefore there exist three design variables to be determined to minimize the cylinder force within the rotating range of floodgate. First, the mathematical model of the roller-link type rotating floodgate is derived to find the cylinder force corresponding to the floodgate angle. Then, the optimal locating point of hydraulic cylinder is searched using the complex method that is one kind of constrained direct search method.

Research on the cable-driven endoscopic manipulator for fusion reactors

  • Guodong Qin;Yong Cheng;Aihong Ji;Hongtao Pan;Yang Yang;Zhixin Yao;Yuntao Song
    • Nuclear Engineering and Technology
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    • v.56 no.2
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    • pp.498-505
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    • 2024
  • In this paper, a cable-driven endoscopic manipulator (CEM) is designed for the Chinese latest compact fusion reactor. The whole CEM arm is more than 3000 mm long and includes end vision tools, an endoscopic manipulator/control system, a feeding system, a drag chain system, support systems, a neutron shield door, etc. It can cover a range of ±45° of the vacuum chamber by working in a wrap-around mode, etc., to meet the need for observation at any position and angle. By placing all drive motors in the end drive box via a cable drive, cooling, and radiation protection of the entire robot can be facilitated. To address the CEM motion control problem, a discrete trajectory tracking method is proposed. By restricting each joint of the CEM to the target curve through segmental fitting, the trajectory tracking control is completed. To avoid the joint rotation angle overrun, a joint limit rotation angle optimization method is proposed based on the equivalent rod length principle. Finally, the CEM simulation system is established. The rationality of the structure design and the effectiveness of the motion control algorithm are verified by the simulation.