• Title/Summary/Keyword: Steam Power Plant

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Assessment of Residual Life for In-Service Fossil Power Plant Components Using Grain Boundary Etching Method (입계부식법에 의한 사용중인 화력발전소 요소의 잔여수명평가)

  • Han, Sang-In;Yoon, Kee-Bong;Chung, Se-Hi
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.21 no.1
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    • pp.22-31
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    • 1997
  • The grain boundary etching method as a method for assessing degradation of structural materials has received much attention because it is simple, inexpensive and easy to apply to real components. In this study, the effectiveness of the method is verified by successfully applying the technique to in-service components of aged fossil power plants such as main steam pipes, boiler headers an turbine rotors. A new degradation parameter, intersecting number ratio (N$_{1}$/N$_{0}$), is employed. The intersecting number ratio (N$_{1}$/N$_{0}$) is defined as the ratio of intersection number (N$_{1}$) obtained from 5-minute picric acid etched surface to the number (N$_{0}$) obtained from nital etched surface. Two kinds of test materials, 2.25Cr-1Mo steel and 1Cr-1Mo-0.25V steel, were artificially thermal-aged at 630.deg. C in different levels of degradation., (N$_{1}$/N$_{0}$) were measured. And, correlations between the measured values and LMP values calculated from aging temperature and aging time were sought. To check the validity of the correlations obtained in laboratory, similar data were measured from service components in four old Korean fossil power plants. These on-site measurement data were in good correlation with those obtained in the laboratory.oratory.

Feasibility Study for Low Pressure Turbine Inspection of Nuclear Power Plant Using Shear Wave Phased Array Ultrasonic Transducer (횡파 위상배열 초음파탐촉자를 이용한 원자력발전소 저압 터빈 검사 적용 타당성 연구)

  • Yoon, Byung Sik;Kim, Yong Sik;Kim, Jin Hoi
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.9 no.1
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    • pp.8-14
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    • 2013
  • Steam turbine blades and discs of nuclear power plants are one of the most highly stressed areas of turbine rotor, and periodic inspection of the blade roots is essential for monitoring integrity and preventing turbine failure. Ultrasonic technique is applied for volumetric inspection of blade root. However, the complexity of blade root geometry imposes challenges to inspection of blades and discs. Recently, phased array ultrasonic inspection technology is being applied to numerous power generation inspection applications including turbine rotor. The phased array ultrasonic technique requires customized inspection wedges which are generally necessary to generate effectively higher incident angle. But the usage of this wedge can cause access limitation for the lower stage blades of turbine because of the wedge front length. Therefore, the shear wave phased array probe which can generate high inspection angle without wedge is essentially necessary. In this study, feasibility study is conducted for the shear wave phased array ultrasonic probe application to blade and disc inspection. As results, the experimental results show that the shear wave phased array probe can detect the flaw and measure its size with reliable accuracy. Therefore if this shear wave phased array probe is applied to field inspection of blade and disc, more reliable inspection is expected for turbine having access limitation.

Mechanism Diagnosis and Avoidance Design on Transient Acoustic Vibration of Reheater Water Supply Piping in Supercritical Boiler (초임계 보일러 재열기 급수 공급배관의 과도 음향진동 진단 및 회피설계)

  • Kim, Yeon-Whan;Bae, Yong-Chae;Kim, Jae-Won;Lee, Doo-Young;Heo, Hae-Yong
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.23 no.5
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    • pp.385-393
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    • 2013
  • In this paper, the mechanism identification and the avoidance measures on the phenomena of transient acoustic vibration amplified at the water-supply piping system to regulate the steam temperature of the boiler reheater in 500MW class supercritical power plant are presented. The pressure pulsation waves induced by the impeller passing of two feed-water pumps with five blades are coincident with the local acoustic modes of boiler reheater water-supply piping system. There are the phenomena amplified at the peaks of 5X, 10X, 15X and 20X in spectrums of piping vibration, sound pressure, and the feed-water's pressure pulsation waves. The shut-off device is installed in the piping system for the interception of pressure pulsation waves transmitted from two feed-water pumps and the modified design change of the piping layout is applied for the acoustic resonance avoidance. The acoustic natural frequencies are separated from the harmonics of pressure pulsation waves induced by the pump impellers passing through the design change of the span length. The acoustic vibration is gone by resonance avoidance measures. As a result, more than 20 dBA reduction is achieved from 100 dBA to 80 dBA.

Simulated Experiments on High Pressure Melt Ejection in the Reactor Cavity During Severe Accident (원자로 가상사고시(노심) 용융물 고압 분출 모의 실험 연구)

  • Jeong, Han-Won;Kim, Do-Hyeong;Lee, Gyu-Jeong;Kim, Sang-Baek;Park, Rae-Jun;Kim, Hui-Dong
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.24 no.11
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    • pp.1447-1456
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    • 2000
  • Simulated experiments of high pressure melt ejection(HPME) are performed to measure the released fraction of corium simulant from the French type PWR cavity. The experiments are carried out on a 1/20th linear scaled model of the Ulchin 1&2 cavity. Water or woods metal and nitrogen is used as simulant of molten corium and steam, respectively. Experimental parameters are water mass, annulus area and breach size. It is shown that only breach size effects is very important while the mass and the annulus area do not affect the released fraction. It is found that the liquid film transport is much more dominant mechanism than the entrainment droplet transport, especially in linear scale down simulated HPME experiment.

A Study on the Vibration Reduction Method for Main steam Piping in Nuclear Power Plant (원자력발전소 주증기관의 진동감쇠 연구)

  • Kim, Yeon-Whan;Kim, Jong-Yeob;Lee, Hyun
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 1996.04a
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    • pp.215-220
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    • 1996
  • 원자력발전소의 주증기관은 증기발생기와 터빈을 연결하는 주요 계통으로서 여기서 발생하는 배관진동은 주요기기의 연결부, 밸브, 배관지지물과 건물 등에 복합적인 반복하중을 가하여 관련 지지물 및 구조물에 열화현상을 발생시켜 발전소의 안전운전에 심각한 영향을 초래할 가능성을 항상 내포하고 있다. 그럼에도 불구하고 배관진동 대책은 대부분 지지물을 추가로 설치하여 진동준위만 낮추고 있는 실정이다. 따라서 구체적인 배관진동의 예측, 측정 및 평가, 감쇠방안에 이르는 종합적이고 체계적인 연구가 요구되고 있다. 본 연구에서는 지지물의 열화현상 및 부분적인 파손으로 진동준위가 높아진 것으로 추정되는 원자력발전소 주증기관의 진동특성 및 요인을 분석하여 진동감쇠 방안을 도출하고 검증함으로써 배관 및 주변 구조물의 건전성을 확보하고 설비의 신뢰성을 확보하고자 하였다. 이를 위하여 주증기관을 모델링하여 해석하였으며, 발전소의 기동 및 정상운전시의 진동준위를 측정하였다. 또한 발전소의 정진기간중 일부 배관계에 대한 실험적 모우드 해석을 수행하였다. 여러가지 진동감쇠 방안을 검토하여 탄성지지 및 에너지 흡수효과를 동시에 발휘할 수 있는 특수 지지물(WEAR$_{TM}$)을 설치하는 방안을 도출하였으며, 현장에 설치한 후 배관의 진동상태를 확인함으로서 효과적인 방안임을 검증하였다.

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Running Bucket Vibration Test of Steam Turbines (증기 터빈 버킷의 회전 진동 시험)

  • 박종포;신언탁;김호종
    • Journal of KSNVE
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    • v.8 no.2
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    • pp.331-335
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    • 1998
  • A design modification was made on the 9-th stage wheel dovetail of a high-intermediate pressure (HIP) turbine rotor for a fossil power plant that necessitates the use of new long-shank buckets for the row. A bucket vibration test is necessary to verify that the new 9-th stage buckets have adequate frequency margin from a nozzle passing frequency when running at speed. A finite element analysis (FEA) has been performed using a commercial S/W to approximately estimate bucket natural frequencies, and thus to help the vibration test. A row of the new buckets has assembled on the HIP rotor for the vibration tests using dynamic balancing facilities. The tests have been done during deceleration run with air excitation. The test results are compared with the calculation using our empirical formula, and show that the modified design meets the frequency-margin requirements.

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Stress Corrosion Cracking Behavior of Alloy 690 in Crevice Environment (Pb + S + Cl) in a Steam Generator Tube (증기발생기 전열관 틈새복합환경(Pb+S+Cl)에서 Alloy 690의 응력부식균열거동)

  • Shin, Jung-Ho;Lim, Sang-Yeop;Kim, Dong-Jin
    • Corrosion Science and Technology
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    • v.17 no.3
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    • pp.116-122
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    • 2018
  • The secondary coolant of a nuclear power plant has small amounts of various impurities (S, Pb, and Cl, etc.) introduced during the initial construction, maintenance, and normal operation. While the concentration of impurities in the feed water is very low, the flow of the cooling water is restricted, so impurities can accumulate on the Top of Tubesheet (TTS). This environment is chemically very complicated and has a very wide range of pH from acidic to alkaline. In this study, the characteristics of the oxide and the mechanism of stress corrosion cracking (SCC) are investigated for Alloy 690 TT in alkaline solution containing Pb, Cl, and S. Reverse U-bend (RUB) specimens were used to evaluate the SCC resistance. The test solution comprises 3m NaCl + 500ppm Pb + 0.31m $Na_2SO_4$ + 0.45m NaOH. Experimental results show that Alloy 690 TT of the crevice environment containing Pb, S, and Cl has significant cracks, indicating that Alloy 690 is vulnerable to stress corrosion cracking under this environment.

Flame Detection of Steam Boilers using Neural Networks and Image Information (영상신호와 신경회로망을 이용한 보일러 화염 검출)

  • Bae, Hyeon;Park, Dong-Jae;Ahan, Hang-Bae;Kim, Sung-Shin
    • Journal of the Korean Institute of Intelligent Systems
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    • v.13 no.2
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    • pp.163-168
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    • 2003
  • Several equipments for flame detection are employed in the power generations. But these flame detectors have some problems for the correct performance. So in this paper, we apply different techniques for the flame detection. Image processing techniques are broadly applied in industrial fields. In this paper, the image information is recorded by a camcoder and then these images are preprocessed for the input values of neural network model. We can test and evaluate the approach that uses image information for the flame detection of burners. If this technique is implemented in physical plant, the economical and effective operation could be achieved.

FLB Event Analysis with regard to the Fuel Failure

  • Baek, Seung-Su;Lee, Byung-Il;Lee, Gyu-Cheon;Kim, Hee-Cheol;Lee, Sang-Keun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05b
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    • pp.622-627
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    • 1996
  • Detailed analysis of Feedwater Line Break (FLB) event for the fuel failure point of view are lack because the event was characterized as the increase in reactor coolant system (RCS) pressure. Up to now, the potential of the rapid system heatup case has been emphasized and comprehensively studied. The cooldown effects of FLB event is considered to be bounded by the Steam Line Break (SLB) event since the cooldown effect of SLB event is larger than that of the FLB event. This analysis provides a new possible path which can cause the fuel failure. The new path means that the fuel failure can occur under the heatup scenario because the Pressurizer Safety Valves (PSVs) open before the reactor trips. The 1000 MWe typical C-E plant FLB event assuming Loss of Offsite Power (LOOP) at the turbine trip has been analyzed as an example and the results show less than 1% of the fuel failure. The result is well within the acceptance criteria. In addition to that, a study was accomplished to prevent the fuel failure for the heatup scenario case as an example. It is found that giving the proper pressure gap between High Pressurizer Pressure Trip (HPPT) analysis setpoint and the minimum PSV opening pressure could prevent the fuel failure.

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Manufacturing 2.25Cr-1Mo Steel In Hot Rolling Strip Mill (2.25% Cr-1%Mo 합금계 열연강판 제조기술)

  • 노태훈
    • Proceedings of the Korean Society for Technology of Plasticity Conference
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    • 1999.08a
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    • pp.390-398
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    • 1999
  • The thermomechanical control process(in hot rolling strip mill) was employed to produce 2.25Cr-1Mo steel, which is to be construction material for the steam generator for power plant. Although the Conventional processes has been the primary means of producing the 2.25Cr-1Mo steel, an alternative method was used to meet the specification of ASTM heat treatment for A387-22-Classl using autotempering after coiling in hot rolling strip mill. The microstructures, tensile properties at various temperatures, and creep-rupture properties have been investigated to compare the properties with those of materials produced by the conventional process and to certify the application of the thermomechanical control process to an actual process of manufacturing 2.25-Cr-1Mo steel, this in turn, will reduce the cost of the process. About 14 to 34% glanular bainite (remainder proetectoid ferrite) formed in a coil, and this variety of volume fraction stems from the different cooling rates, which varies with position of the coil after coiling. Tensile testing from room temperature to 700$^{\circ}C$ indicated that strength increases with test temperature showing peaks at around 600$^{\circ}C$. Creep-rupture properties have been being investigated at the temperature of 500$^{\circ}C$ with 27.5, 32kg/$\textrm{mm}^2$ loads and have showed no rupture for over 1000 hours.

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