• Title/Summary/Keyword: Load Rejection Test

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Field Adaptability Test for the Full Load Rejection of Nuclear Turbine Speed Controllers using Dynamic Simulator

  • Choi, In-Kyu;Kim, Jong-An;Woo, Joo-Hee
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.23 no.7
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    • pp.67-74
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    • 2009
  • This paper describes the speed control functions of the typical steam turbine speed controllers and the test results of generator load rejection simulations. The goal of the test is to verify the speed controller's ability to limit the steam turbine's peak speed within a predetermined level in the event of generator load loss. During normal operations, the balance between the driving force of the steam turbine and the braking force of the generator load is maintained and the speed of the turbine-generator is constant. Upon the generator's load loss, in other word, the load rejection, the turbine speed would rapidly increase up to the peak speed at a fast acceleration rate. It is required that the speed controller has the ability to limit the peak speed below the overspeed trip point, which is typically 110[%] of rated speed. If an actual load rejection occurs, a substantial amount of stresses will be applied to the turbine as well as other equipments, In order to avoid this unwanted situation, not an actual test but the other method is necessary. We are currently developing the turbine control system for another nuclear power plant and have plan to do the simulation suggested in this paper.

Estimation of PTC (Powertrain Cooling) Performance with Heat Rejection Rate (열방출량 (Heat Rejection Rate)을 이용한 PTC (Powertrain Cooling) 성능 추정)

  • Min, Sunki
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.16 no.5
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    • pp.3030-3034
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    • 2015
  • It is important to consider powertrain cooling performance, when engine is applied to new vehicle. If the performance is poor, engine will be damaged by overheating. But, the development timing of engine is faster than timing of vehicle, it is difficult to test the cooling performance of new engine and vehicle. In this study the powertain cooling performance was estimated with some test and calculation data. First, the heat rejection test was conducted. From this test, the heat rejection data at required rpm and load was acquired. Second, coolant flow test was conducted. From this test coolant flow rate to radiator was measured. Then engine torque and rpm was calculated from vehicle load and speed. Vehicle load and speed was calculated from test mode. Then by comparing these data, the powertrain cooling performance was estimated.

Modeling and verification of generator/control system of Seo-Inchon combined-cycle plant by load rejection test (부하차단시험에 의한 서인천복합화력 발전기.제어계의 모델링 및 검증)

  • 최경선;문영환;김동준;추진부;류승헌;권태원
    • The Transactions of the Korean Institute of Electrical Engineers
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    • v.45 no.4
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    • pp.501-510
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    • 1996
  • The gas-turbine generator of Seo-Incheon combined-cycle plant was tested for derivation of a model for dynamic analysis. Load rejection and AVR step test was performed to get the dynamic response of generator. The parameters of generator/control system model were determined by these measured data. No-load saturation test was performed for the saturation characteristics of the generator under steady state. V-curve test was also performed so as to find exact generator parameters. Q-axis parameters of generator was derived by measuring power angle. AVR and governor constants have been tuned by their oscillatory period and setting time characteristics. The derived parameters of generator control system is verified by one-machine infinite bus system simulation. (author). 7 refs., 20 figs., 5 tabs.

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A Simulation Test of Load Rejection for Steam Turbine Generator in a 680MW Nuclear Power Plant (680MW 원자력발전소 증기터빈 발전기의 부하차단 모의시험)

  • Choi, In-Kyu;Jeong, Chang-Ki
    • Proceedings of the KIEE Conference
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    • 2007.07a
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    • pp.1605-1606
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    • 2007
  • An electrical generator in power plant is driven and maintained its speed at rated by steam turbine. By the way, after synchronization in parallel with the power system, as the steam flow into turbine can not be reduced fast even though the electrical load is lost, the turbine gets into dangerous situation due to the increase of its speed. At this time, the duty of the turbine governor is to limit the speed to its overspeed trip set point by stopping the steam flow as soon as possible, the test of which is called load rejection test. It is introduced in this paper for a field simulation test of generator load rejection to be implemented on the turbine governor in a 680MW nuclear power plant before its startup.

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A simulation test of lone rejection for steam turbine generator in nuclear power plant (원자력발전소 증기터빈 발전기의 부하차단 모의시험)

  • Choi, In-Kyu;Jeong, Tae-Woon;Lee, Ki-Seong
    • Proceedings of the KIEE Conference
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    • 2003.07d
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    • pp.2301-2303
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    • 2003
  • A steam turnine in thermal/nuclear power plant drives generator and maintains it at rated speed using high temperature and high pressure steam energy. After synchronization in parallel with the power system, generator output increases according as the governor, that is the controller, increases steam flow into turbine. By the way, as the steam flow into turbine can not be reduced fast even though the electrical load is lost, the turbine gets into dangerous situation due to the increase of its speed. At this time, the duty of the turbine governor is to limit the speed to its overspeed trip setpoint by stopping the steam flow as soon as possible, the test of which is called load rejection test. It is introduced in this paper for a simulation test of generator load rejection to be implemented on the turbine governor in a 600MW nuclear power plant before its startup.

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Evaluation of Load Rejection to House Load Test at 100% Power for YGN 4

  • Sohn, Jong-Joo;Jeong, Won-Sang;Chi, Sung-Goo;Seo, Jong-Tae;Kim, Si-Hwan
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05a
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    • pp.588-595
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    • 1995
  • The Load Rejection to House Load test at 100% power was successfully performed during the YGN 4 PAT period. In this test, all plant control systems automatically controlled the plant from 100% power to house load operation mode. The LTC code, which was used in the performance analysis during the design process of YGN 3&4, predictions of the test agreed with the measured data demonstrating the validity of the code as well as the completeness of the plant design.

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Evaluation of Load Rejection to House Load Test at 50% Power for UCN 3

  • Lee, Chang-Gyun;Suk whun Sohn;Sohn, Jong-Joo;Seo, Jong-Tae;Lee, Sang-Keun;Kim, Youngsung;Nam, Kyu-Won;Jung, Yang-Mook;Chae, Kyeong-Sik
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.398-403
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    • 1998
  • The Load Rejection to House Load test at 50% power was successfully peformed during the UCN 3 PAT period. In this test, all plant control systems automatically controlled the plant from 50% power to house load operation mode. The KISPAC code, which was used in the performance analysis during the design process of UCN 3&4, predictions of the test agreed with the measured data demonstrating the validity of the code as well as the completeness of the plant design.

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Load Test Simulator Development for Steam Turbine-Generator System of Nuclear Power Plant

  • Jeong, Chang-Ki;Kim, Jong-An;Kim, Byung-Chul;Choi, In-Kyu;Woo, Joo-Hee
    • 제어로봇시스템학회:학술대회논문집
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    • 2005.06a
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    • pp.1384-1386
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    • 2005
  • This paper focuses on development of load test simulator of a steam turbine-generator in a nuclear power plant. When load is taken off from electrical power network, it is very difficult to effectively control the steam flow to turbine of the nuclear turbine-generator, because of disturbances, such as electrical load and network unbalance on electrical network. Up to the present time, the conventional control system has been used for the load control on nuclear steam generator, owing to the easy control algorithms and the advantage which have been proven on the nuclear power plant. However, since there are problems with stability control during low power and start-up, only a highly experienced operator can operate during those procedures. Also, a great deal of time and an expensive simulator is needed for the training of an operator. The KEPRI is developed simulator for 600MW nuclear power plant to take a test of generator load rejection, throttle valve, and turbine load control. Total load test is implemented before start up.

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A Study on Effect of Scale Formation in Water Jacket on Thermal Durability in LPG Engine (엔진 물통로 내부 벽면 스케일 축적이 LPG 엔진의 열적 내구성에 미치는 영향에 대한 연구)

  • 류택용;신승용;최재권
    • Transactions of the Korean Society of Automotive Engineers
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    • v.9 no.3
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    • pp.42-50
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    • 2001
  • In this paper, the effects of scale formation in engine water jacket upon the thermal durability of engine itself and its component parts were studied. To understand the effect of quality of water, a full load engine endurance test for 50 hours was carried out with not-treated underground water. The followings were found through the tested engine inspection after the endurance test; 1-2 mm thick scale formation in the engine water jacket, valve seat wear, piston top land scuffing, piston pin stick, and cylinder bore scuffing in siamese area. In order to understand the causes of above test results, the heat rejection rate to coolant, the metal surface temperature of combustion chamber, and the oil and exhaust gas temperatures were measured and analyzed. The scale formed in the engine water jacket played a role as thermal insulator. The scale formed in the engine reduced the heat rejection rate to coolant and it caused to increase the metal surface temperature. The reduced heat rejection rate to coolant increased the heat rejection rate to oil and exhaust gas and increased the oil and exhaust gas temperature. Also, the reasons of valve seat wear, piston top land scuffing and cylinder bore scuffing, and piston pin stick quantitatively analyzed in this paper.

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Characteristics of Synchronous and Asynchronous modes of fluctuations in Francis turbine draft tube during load variation

  • Goyal, Rahul;Cervantes, Michel J.;Gandhi, Bhupendra K.
    • International Journal of Fluid Machinery and Systems
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    • v.10 no.2
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    • pp.164-175
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    • 2017
  • Francis turbines are often operated over a wide load range due to high flexibility in electricity demand and penetration of other renewable energies. This has raised significant concerns about the existing designing criteria. Hydraulic turbines are not designed to withstand large dynamic pressure loadings on the stationary and rotating parts during such conditions. Previous investigations on transient operating conditions of turbine were mainly focused on the pressure fluctuations due to the rotor-stator interaction. This study characterizes the synchronous and asynchronous pressure and velocity fluctuations due to rotor-stator interaction and rotating vortex rope during load variation, i.e. best efficiency point to part load and vice versa. The measurements were performed on the Francis-99 test case. The repeatability of the measurements was estimated by providing similar movement to guide vanes twenty times for both load rejection and load acceptance operations. Synchronized two dimensional particle image velocimetry and pressure measurements were performed to investigate the dominant frequencies of fluctuations, vortex rope formation, and modes (rotating and plunging) of the rotating vortex rope. The time of appearance and disappearance of rotating and plunging modes of vortex rope was investigated simultaneously in the pressure and velocity data. The asynchronous mode was observed to dominate over the synchronous mode in both velocity and pressure measurements.