• Title/Summary/Keyword: plant pipe

Search Result 473, Processing Time 0.028 seconds

Demonstration of EPRI CHECWORKS Code to Predict FAC Wear of Secondary System Pipings of a Nuclear Power Plant

  • Lee, Sung-Ho;Seong Jegarl;Chung, Han-Sub
    • Nuclear Engineering and Technology
    • /
    • v.31 no.4
    • /
    • pp.375-384
    • /
    • 1999
  • The credibility of CHECWORKS FAC model analysis was evaluated for plant application in a model plant chosen for demonstration. The operation condition at each pipe component was defined before the wear rate analysis by plant data base, water chemistry analysis, and network flow analysis. The predicted wear was compared with the measured wear for 57 sample components selected from 43 susceptible line groups analysed. The inspected 57 locations represent components of highest predicted wear in each line group. Both absolute value and relative ranking comparisons indicated reasonable correlations between the predicted and the measured values. Four components showed much higher measured wear rates than the predicted ones in the feed water train from main feed water pump discharge to steam generator, probably due to high hydrazine concentration operation the effect of which had not been incorporated into the CHECWORKS model. The measured wear was higher than the predicted one consistently for components with least susceptibility to FAC. It is believed that the conservatism maintained during UT data analysis dominated the measurement accuracy. A great deal of enhancement is anticipated over the current plant pipe management program when a comprehensive plant pipe management program is implemented based on the model analysis.

  • PDF

Development for Life Assessment System for Pipes of Thermal Power Plants

  • Hyun, Jung-Seob;Heo, Jae-Sil;Kim, Doo-Young;Park, Min-Gyu
    • KEPCO Journal on Electric Power and Energy
    • /
    • v.2 no.4
    • /
    • pp.583-588
    • /
    • 2016
  • The high-temperature steam pipes of thermal power plants are subjected to severe conditions such as creep and fatigue due to the power plant frequently being started up and shut down. To prevent critical pipes from serious damage and possible failure, inspection methods such as computational analysis and online piping displacement monitoring have been developed. However, these methods are limited in that they cannot determine the life consumption rate of a critical pipe precisely. Therefore, we set out to develop a life assessment system, based on a three-dimensional piping displacement monitoring system, which is capable of evaluating the life consumption rate of a critical pipe. This system was installed at the "M" thermal power plant in Malaysia, and was shown to operate well in practice. The results of this study are expected to contribute to the increase safety of piping systems by minimizing stress and extending the actual life of critical piping.

Integrity Evaluation of Ice Plugged Pipes Applied on Short Jacket

  • Park, Yeong-Don;Son, Geum-Su
    • Nuclear Engineering and Technology
    • /
    • v.34 no.2
    • /
    • pp.105-116
    • /
    • 2002
  • In special industrial fields such 3s nuclear power plants and chemical plants, it is often necessary to repair system components without plant shutdown or drainage of system having many piping structures which may have hazardous or expensive fluid. A temporary ice plugging method for blocking internal flow is considered as a useful method in that case. According to the pipe freezing guideline of the nuclear power plant, the length of a freezing jacket must be longer than twice of the pipe diameter. However, for applying the ice plugging to short pipes which do not have enough freezing length because of geometrical configuration, it is inevitable to use shorter jacket less than twice of the pipe diameter. In this study, the integrity evaluation for short pipes in the nuclear power plant Is conducted by an experiment and the finite element analysis. From the results, the ice plugging process in short pipes can be safely carried out without any plastic deformation and fracture.

A Study on Removing the Magnetic Impurity in a Power Plant Line (발전소 배관 내부유체의 자성 이물질 제거에 관한 연구)

  • Choi, Yoon-Hwan;Kim, Oh-Kuen;Suh, Yong-Kweon
    • The KSFM Journal of Fluid Machinery
    • /
    • v.6 no.4 s.21
    • /
    • pp.45-49
    • /
    • 2003
  • This work focuses on eliminating tiny particles from the coolant in a nuclear pipe line by using a permanent magnet on the exterior surface of the pipe. This method have some merits compared with the currently applied methods and is expected to be applied to most of the pipe lines in the nuclear plant. For instance in this method, a ring is attacked to the exterior surface of the pipe, so that it does not affect the inflows directly. Further, the cost needed in the initial build-up of the facility is low.

Computational Study of Energy Loss in a Pipe of Refuse Collecting System (쓰레기 관로운송 시스템의 운송에너지 손실에 관한 수치해석적 연구)

  • Lee, Jong-Gil;Choi, Yoon;Hong, Ki-Chul;Choi, Young-Don
    • Proceedings of the SAREK Conference
    • /
    • 2009.06a
    • /
    • pp.421-426
    • /
    • 2009
  • This paper describes on energy loss in a pipe of refuse collecting system. Analysis energy loss in a pipe is the decisive factor in a design for refuse collecting system. From the analysis energy loss, we can determine the capacity of turbo blower. The flow characteristics in the pipe with the refuse bag are analyzed by three-dimensional Navier-Stokes analysis. The refuse bag is modeled using the actual measurement. We obtain friction factor by changing refuse bag's size and mixing ratio and Reynolds number. And From the result we calculate energy loss by using compressible flow analysis.

  • PDF

Study of Thermal Stratification into Leaking Flow in the Nuclear Power Plant, Emergency Core Coolant System (원자로 비상 냉각재 누설에 의한 열성층의 비정상 특성에 관한 연구)

  • Han Seong-Min;Choi Yong-Don;Park Min-Soo
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
    • /
    • v.18 no.3
    • /
    • pp.202-210
    • /
    • 2006
  • In the nuclear power plant, emergency core coolant system (ECCS) is furnished at reactor coolant system (RCS) in order to cool down high temperature water in case of emergency. However, in this coolant system, thermal stratification phenomenon can be occurred due to coolant leaking in the check valve. The thermal stratification produces excessive thormal stresses at the pipe wall so as to yield thermal fatigue crack (TFC) accident. In the present study, when the turbulence penetration occurs in the branch pipe, the maximum temperature differences of fluid at the pipe cross-sections of the T-branch with thermal stratification are examine.

Discrimination of Plant Transient by Using the Fuzzy Pattern Recognition (퍼지 패턴인식법을 이용한 발전소 과도상태 판별)

  • Kim Jong-Seog;Lee Dong-ju
    • Transactions of the Korean Society of Machine Tool Engineers
    • /
    • v.14 no.1
    • /
    • pp.37-43
    • /
    • 2005
  • Plant pipe has a fatigue life which is induced by repeated stress come from the variation of temperature and pressure. To avoid the fatigue crack of plant pipe which is produced by long term repeated stress, plant operator has to limit the mont of operating transient. This paper introduced the study result about discrimination methodology of plant transient by using the fuzzy pattern recognition. As result of applying the fuzzy pattern recognition to actual plant operation data, it is confirmed that fuzzy pattern recognition methodology can be useful for the comparison of similarity for the transients of similar output but has different time pattern.

A Study of the Sectionalizing for Pipe Deterioration Evaluation in Industrial Facilities (산업시설 배관 노후도 평가를 위한 배관 섹션화 방안 연구)

  • Min, Hyuk-Ki;Kim, Sang-Bum;Kim, Byung-Woo;Kim, Hyoung-Ki;Park, Yool
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
    • /
    • v.27 no.2
    • /
    • pp.103-111
    • /
    • 2015
  • In general, no particularly well-established standards have been in place so far, for the method of evaluating the deteriorated level of pipes and ducts of industrial facilities. For that reason, the evaluation depends upon various studies which are based on the analysis of the residual life, thickness thinning, closure rate, and scale thickness that measure a few specific positions of pipes. It also depends upon the expertise in business operation and the specific techniques conducted by the inspection companies and institutions. This research introduces the concept of measuring units per section and the selection method of measurement points per section. Furthermore, specific methodologies were developed to plan and analyze deterioration level of industrial pipes and ducts by engineers and managers using a section map. Consequently, applying the outcomes from this study to the plant equipment of the incineration facility resulted in saving 42% of the repairing and remodeling cost.

Study on the Systematic Technology of Promoting Purification for the Livestock Wastewater and Reuse

  • Okada, Yoshiichi;Shim, Jae-Do;Mitarai, Masahumi;Kojima, Takayuki;Gejima, Yoshinori
    • Proceedings of the Korean Society for Agricultural Machinery Conference
    • /
    • 1996.06c
    • /
    • pp.692-700
    • /
    • 1996
  • The objective of this study is to develop a systematic purification plant using the metabolism of aerobic microorganisms. This system is subsequently aerated and continuously removes suspended solids and settling sludges caused by aerating pressure at the bottom of a lower pipe (i.e., Continuous Removal of Suspended solids and Settling sludges, CRSS). The CRSS plants are brought out by introducing fine air bubbles into the liquid phase of a lower pipe in the bio-reactor. These plant uses aeration pipe, with multiple inlets to sweep the floor of bio-reactor tank, instead of the conventional scraper mechanisms. The principal advantage of this system is that it can continuously remove very small or light particles that settles completely within a short time. Once the particles have been floated to the surface, they can be moved into the pipe and collected in the settling tank by sequently aerated pressure. The experimental results shows that about 99.0% of the biochemical oxygen demand(BOD), 99.3% of the suspended solid(SS), 92.3% of the total nitrogen(T-N), 99.0% of the turbidity(TU), 100% of the total coliform(TC)and ammonia was respectively removed during aerobic digestion for 9 days. These result indicates that the CRS S plants are very effective for reduction and deodorization of swine wastewater contaminants, and the efflux from CRS S can either be discharged in the river or used as nutrient solution of formulation for plant growth factories. The developed CRSS plant proved to be flexible and it can simply be adapted to any type of biological waste treatment problem.roblem.

  • PDF

Countermeasure on High Vibration of Branch Pipe with Pressure Pulsation Transmitted from Main Steam Header (주증기 배관 헤더의 압력맥동에 대한 분기 배관의 고진동 대책)

  • Kim, Yeon-Whan;Bae, Yong-Chae;Lee, Young-Shin
    • Transactions of the Korean Society for Noise and Vibration Engineering
    • /
    • v.15 no.8 s.101
    • /
    • pp.988-995
    • /
    • 2005
  • Vibration has been severly increased at the branch pipe of main steam header since the commercial operation of nuclear power plant. Intense broad band disturbance flow at the discontinuous region such as elbow, valve, and header generates the acoustical pulsation which is propagated through the piping system. The pulsation becomes the source of low frequency vibration at piping system. If it coincide with natural frequency of the pipe system, excessive vibration is made. High level vibration due to the pressure pulsation related to high dynamic stress, and ultimately, to failure probability affects fatally the reliability and confidence of plant piping system. This paper discusses vibration effect for the branch pipe system due to acoustical pulsations by broad band disturbance flow at the large main steam header in 700 MW nuclear power plant. The exciting sources and response of the piping system are investigated by using on-site measurements and analytical approaches. It is identified that excessive vibration is caused by acoustical pulsations of 1.3 Hz, 4.4 Hz and 6.6 Hz transmitted from main steam balance header, which are coincided with fundamental natural frequencies of the piping structure. The energy absorbing restraints with additional stiffness and damping factor were installed to reduce excessive vibration.