• Title/Summary/Keyword: Core Pump System

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Resistivity Monitoring of Saturated Rock Cores at Room Temperature (수포화 암석코어의 상온 전기비저항 모니터링)

  • Lee, Sang Kyu;Lee, Tae Jong;Yi, Myeong-Jong
    • Geophysics and Geophysical Exploration
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    • v.18 no.3
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    • pp.105-114
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    • 2015
  • A long-term resistivity monitoring system has been developed for saturated cores in room temperature and humidity condition. A 3-channel water-pump continuously drops the water onto the top of saturated core sample surrounded by shrinkable tube as well as on the paper filters of the electrodes at both sides of the core sample, by which one can monitor the resistivity changes with maintaining full saturation of the rock core for a week or longer. Monitoring the resistivity changes has been performed with 3 kinds of rock samples including biotite gneiss, andesitic tuff, and shale for 9 days using the system. Consequently, it is proposed two hypothesis that conversion speed of temperature coefficient has close relation to the thermal properties of the rock sample and that the ratio of resistance between dry and saturated conditions for a rock sample can be related to the effective porosity of the sample. The ratio between dry and saturated resistance for the three rock types are 48, 705, and 2, while effective porosity was 3.7%, 3.3%, and 13.0%, respectively.

Reaction Characteristics of LPG fuel in LPLi fuel supply system (LPLi연료시스템의 LPG연료 반응성 연구)

  • Kim, Chang-Up;Park, Cheol-Woong;Kang, Kern-Yong
    • Proceedings of the KSME Conference
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    • 2008.11b
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    • pp.2904-2909
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    • 2008
  • The liquid phase LPG injection (LPLi) system (the 3rd generation technology) has been considered as one of the more promising fuel supply systems for LPG vehicles. To investigate the characteristics of LPG residue in LPLi system, various rubbers were reacted with LPG fuels. The results showed that the residue of a cover rubber in a fuel pump after test increased 10 times higher than that before test. Furthermore, the amount of sulfur, nitrogen species which are considered as main sources in deposit formation in the LPLi fuel injector were also found to be higher than that in original LPG fuel. And these residues made the core parts of LPLi injector such as a neddle and a nozzle, partially worn, which eventually causes a leakage in LPLi injectors.

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A Heat Shock Simulation System for Testing Performance of EWP (EWP 성능 검사를 위한 열 충격 모사시스템)

  • Yoo, Nam-Hyun
    • The Journal of the Korea institute of electronic communication sciences
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    • v.14 no.3
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    • pp.553-558
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    • 2019
  • Global auto parts companies are making efforts to develop EWP(: Electric Water Pump) which is one of the core parts of environment friendly car. In eco-friendly automobiles, an independent cooling system is used rather than a cooling system that is linked to an internal combustion engine. Therefore, the research and development of the water pump operating separately from the engine and the related production system are being actively carried out. In order to overcome the shortcoming of EWP of PPS material suitable for injection system, G company which is a global parts company that researches and develops EWP around SUS and is in the process of developing robot-based production equipment for mass production. In this paper, a heat shock simulation system is designed and implemented that works with the robot-based production system to test the performance of the produced EWP. By using this system, it is possible to test the EWP in an virtual environment similar to the actual environment, thereby reducing the defect rate of the product. At the same time, all the data produced during the entire process for testing can be stored, which can be utilized in the future development of CPS(: Cyber Physical System) of EWP system based on big data.

RELAP5/MOD3 Assessment Against a ROSA-IV/LSTF Loss-of-RHRS Experiment

  • Park, Chul-Jin;Han, Kee-Soo;Lee, Cheol-Sin;Kim, Hee-Cheol;Lee, Sang-Keun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05b
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    • pp.745-750
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    • 1996
  • An analysis of a loss of residual heat removal system (RHRS) event during midloop operation after reactor shutdown was performed using the RELAP5/MOD3 thermal-hydraulic computer code. The experimental data of a 5% cold leg break test conducted at the ROSA-IV Large Scale Test Facility (LSTF) to simulate a main coolant pump shaft seal removal event during midloop operation of a Westinghouse-type PWR were used in the analysis. The predicted core boiling time and the peak primary system pressure showed good agreements with the measured data. Some differences between the calculational results and the experimental results were, however, found in areas of the timing of loop seal clearing and the temperature distribution in a pressurizer. Other calculational problems identified were discussed as well.

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Effect of the Design Parameters of Geothermal Heat Exchanger Design Length (설계변수가 수직밀폐형 지중열교환기 설계길이에 미치는 영향)

  • Min, Kyong-Chon;Choi, Jae-Ho
    • Journal of the Korean Society for Geothermal and Hydrothermal Energy
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    • v.7 no.2
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    • pp.10-15
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    • 2011
  • A ground loop heat exchanger for the ground source heat pump system is the core equipment determining the thermal performance and initial cost of the system The length and performance of the heat exchanger is dependent on the ground thermal conductivity, the operation hours, the ground loop diameter, the grout, the ground loop arrangement, the pipe placement and the design temperature. The result of this simulation shows that higher thermal conductivity of grouting materials leads to the decrease length of geothermal heat exchanger from 100.0 to 84.4%.

Brief description of the Design and Construction of the Burj Dubai Project, Dubai, UAE.

  • Abdelrazaq Ahmad K.
    • Proceedings of the Korea Concrete Institute Conference
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    • 2005.05a
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    • pp.9-14
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    • 2005
  • The Burj Dubai Project will be the tallest structure ever built by man; when completed the tower will be more than 700 meter tall and more than 160 floors. The early integration of aerodynamic shaping and wind engineering considerations played a major role in the architectural massing and design of this residential tower, where mitigating and taming the dynamic wind effects was one of the most important design criteria. This paper presents a brief overview of the structural system development and considerations of the tower and discusses the construction planning of the key structural components of the tower.

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Effect of multiple-failure events on accident management strategy for CANDU-6 reactors

  • YU, Seon Oh;KIM, Manwoong
    • Nuclear Engineering and Technology
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    • v.53 no.10
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    • pp.3236-3246
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    • 2021
  • Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failures should be considered more seriously rather than single failure in the licensing bases and safety cases because attempts to take accident management measures could be unsuccessful under the high radiation environment aggravated by multiple failures, such as complete loss of electric power, uncontrollable loss of coolant inventory, failure of essential safety function recovery. In the case of the complete loss of electric power called station blackout (SBO), if there is no mitigation action for recovering safety functions, the reactor core would be overheated, and severe fuel damage could be anticipated due to the failure of the active heat sink. In such a transient condition at CANDU-6 plants, the seal failure of the primary heat transport (PHT) pumps can facilitate a consequent increase in the fuel sheath temperature and eventually lead to degradation of the fuel integrity. Therefore, it is necessary to specify the regulatory guidelines for multiple failures on a licensing basis so that licensees should prepare the accident management measures to prevent or mitigate accident conditions. In order to explore the efficiency of implementing accident management strategies for CANDU-6 plants, this study proposed a realistic accident analysis approach on the SBO transient with multiple-failure sequences such as seal failure of PHT pumps without operator's recovery actions. In this regard, a comparative study for two PHT pump seal failure modes with and without coolant seal leakage was conducted using a best-estimate code to precisely investigate the behaviors of thermal-hydraulic parameters during transient conditions. Moreover, a sensitivity analysis for different PHT pump seal leakage rates was also carried out to examine the effect of leakage rate on the system responses. This study is expected to provide the technical bases to the accident management strategy for unmitigated transient conditions with multiple failures.

Development of a 3D Printing System for Construction Using an Articulated Robot (다관절 로봇을 이용한 건설용 3D프린팅 출력시스템 개발)

  • Lee, Giryun;Nho, Hyunju;Jung, Namcheol
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2023.11a
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    • pp.263-264
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    • 2023
  • 3D printing technology is recognized as a core technology that will lead the next generation, and is a field that can have a large ripple effect if it innovates the existing construction production method. Therefore, this study deals with the development of a 3d printing system using an articulated robot for construction purposes. In this system, ABB robot was used to control the developed cement gun accurately. The system is composed of mixer to mix cementitious materials, pump to transfer the materials, abb robot to motion control and cement gun to extrude the materials to print required construction parts. Using the system developed in this study, a suitable mix ratio of cementitious materials was found and successively printed a 1m high structure that demonstrated possibility of printing structures using 3d printer. In the future, we plan to build a foundation for automated construction through research on construction methods and materials that can be continuously layered for the system.

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A FLOW AND PRESSURE DISTRIBUTION OF APR+ REACTOR UNDER THE 4-PUMP RUNNING CONDITIONS WITH A BALANCED FLOW RATE

  • Euh, D.J.;Kim, K.H.;Youn, Y.J.;Bae, J.H.;Chu, I.C.;Kim, J.T.;Kang, H.S.;Choi, H.S.;Lee, S.T.;Kwon, T.S.
    • Nuclear Engineering and Technology
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    • v.44 no.7
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    • pp.735-744
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    • 2012
  • In order to quantify the flow distribution characteristics of APR+ reactor, a test was performed on a test facility, ACOP ($\underline{A}$PR+ $\underline{C}$ore Flow & $\underline{P}$ressure Test Facility), having a length scale of 1/5 referring to the prototype plant. The major parameters are core inlet flow and outlet pressure distribution and sectional pressure drops along the major flow path inside reactor vessel. To preserve the flow characteristics of prototype plant, the test facility was designed based on a preservation of major flow path geometry. An Euler number is considered as primary dimensionless parameter, which is conserved with a 1/40.9 of Reynolds number scaling ratio. ACOP simplifies each fuel assembly into a hydraulic simulator having the same axial flow resistance and lateral cross flow characteristics. In order to supply boundary condition to estimate thermal margins of the reactor, the distribution of inlet core flow and core exit pressure were measured in each of 257 fuel assembly simulators. In total, 584 points of static pressure and differential pressures were measured with a limited number of differential pressure transmitters by developing a sequential operation system of valves. In the current study, reactor flow characteristics under the balanced four-cold leg flow conditions at each of the cold legs were quantified, which is a part of the test matrix composing the APR+ flow distribution test program. The final identification of the reactor flow distribution was obtained by ensemble averaging 15 independent test data. The details of the design of the test facility, experiment, and data analysis are included in the current paper.

Performance Evaluation of Large Borehole Ground-Loop Heat Exchanger (저심도 대구경 지중열교환기의 설치조건에 따른 성능 연구)

  • Yoo, Gyu-Sang;Park, Il-Mun;Choi, Jae-Ho;Shin, Hyun-Joon
    • Proceedings of the SAREK Conference
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    • 2009.06a
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    • pp.58-63
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    • 2009
  • A ground-loop heat exchanger for the ground source heat pump system is the core equipment determining the thermal performance and initial cost of the system. The size and performance of the heat exchanger is highly dependent on the ground thermal properties - the ground effective thermal conductivity, the borehole thermal resistance and the undisturbed ground temperature. Nowadays, precast concrete piles using steel reinforced precast concrete piles - energy piles - are used to reduce the installing cost of the ground-loop heat exchanger. We were carried out some tests to investigate the effects of some parameters such as borehole length, grouting materials and U-tube configuration of the energy piles. 4 concrete piles, each measuring $250mm{\sim}400mm$ in diameter and approx. 10m in length, and rigged with single spiral and 3 U-tube loop of $16mm{\times}2.3mm$ PB piping. The thermal response tests were conducted using a testing device for 4-different ground-loop heat exchangers. During the heating period, the energy piles absorb the heat of 0.89kW to 1.37kW.

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