• Title/Summary/Keyword: Piping system

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Evaluation of Piping Failure Probability of Reactor Coolant System in Kori Unit 1 Considering Stress Corrosion Cracking (응력부식균열을 고려한 고리 1호기 원자로냉각재계통의 배관 파손확률 평가)

  • Park, Jeong Soon;Choi, Young Hwan;Park, Jae Hak
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.6 no.1
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    • pp.43-49
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    • 2010
  • The piping failure probability of the reactor coolant system in Kori unit 1 was evaluated considering stress corrosion cracking. The P-PIE program (Probabilistic Piping Integrity Evaluation Program) developed in this study was used in the analysis. The effect of some variables such as oxygen concentration during start up and steady state operation, and operating temperature, which are related with stress corrosion cracking, on the piping failure probabilities was investigated. The effects of leak detection capability, the size of big leak, piping loops, and reactor types on the piping failure probability were also investigated. The results show that (1) LOCA (loss of coolant accident) probability of Kori unit 1 is extremely low, (2) leak probability is sensitive to oxygen concentration during steady state operation and operating temperature, while not sensitive to the oxygen concentration during start up, and (3) the piping thickness and operating temperature play important roles in the leak probabilities of the cold leg in 4 reactor types having same inner diameter.

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Vibration Effect for Branch Pipe System due to Main Steam Header Pulsation (주증기 배관 헤더의 맥동이 분기 배관에 미치는 영향)

  • Kim, Yeon-Whan;Bae, Yong-Chae;Lee, Hyun
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2005.05a
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    • pp.780-785
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    • 2005
  • Vibration has been severly increased at the branch pipe of main steam header since the commercial operation of a nuclear power plant. Intense broad band disturbance flow at the discontinuous region such as elbow, valve or heather 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 7nn nuclear power plant. The exciting sources and response or 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 1.3Hz, 4.4Hz and 6.6Hz transferred from main steam header, which are coincided with fundamental natural frequencies of the piping structure. The energy absorbing restraints with additional stiffness were installed to reduce excessive vibration.

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Seismic Capacity Test of Nuclear Piping System using Multi-platform Shake Table (다지점 진동대를 이용한 원자력발전소 배관계통의 내진성능실험)

  • Cheung, Jin-Hwan;Gae, Man-Soo;Seo, Young-Deuk;Choi, Hyoung-Suk;Kim, Min-Kyu
    • Journal of the Earthquake Engineering Society of Korea
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    • v.17 no.1
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    • pp.21-31
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    • 2013
  • In this study, dynamic characteristics and seismic capacity of the nuclear power plant piping system are evaluated by model test results using multi-platform shake table. The model is 21.2 m long and consists of straight pipes, elbows, and reducers. The stainless steel pipe diameters are 60.3 mm (2 in.) and 88.9 mm (3 in.) and the system was assembled in accordance with ASME code criteria. The dynamic characteristics such as natural frequency, damping and acceleration responses of the piping system were estimated using the measured acceleration, displacement and strain data. The natural frequencies of the specimen were not changed significantly before and after the testing and the failure and leakage of the piping system was not observed until the final excitation. The damping ratio was estimated in the range of 3.13 ~ 4.98 % and it is found that the allowable stress(345 MPa) according to ASME criteria is 2.5 times larger than the measured maximum stress (138 MPa) of the piping system even under the maximum excitation level of this test.

Evaluation of High Cycle Thermal Fatigue on Mixing Tee in Nuclear Power Plant (원전 Mixing Tee에서의 고주기 열피로 평가)

  • Lee, Sun Ki
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.16 no.1
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    • pp.22-29
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    • 2020
  • In nuclear power plants, there is a risk of thermal fatigue in equipment and piping affecting system soundness because the temperature change of the system accompanies in every operation and shutdown. Therefore, in order to prevent the excess of the fatigue limit during the lifetime of plants, the fatigue limit of each piping material is determined in the designing stage. However, there are many cases where equipment or piping is locally subjected to thermal fatigue that is not considered in the design, resulting in damage to the equipment and piping, and failure during operation. Currently, local thermal fatigue generation mechanisms that are not taken into account in the design stage are gradually being identified. In this paper, the effects of the fluid temperature fluctuations on the piping soundness due to the mixing of hot and cold water, one of the local thermal fatigue generating mechanisms, were evaluated.

Rapid Pipe Modeling Method Considering the Relationship with a Hull Structure (선체 구조와의 연관성을 고려한 신속 배관 모델링 방법)

  • Roh, Myung-Il;Choi, Woo-Young;Lee, Kyu-Yeul
    • Journal of the Society of Naval Architects of Korea
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    • v.43 no.2 s.146
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    • pp.258-267
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    • 2006
  • The present piping modeling method requires detailed inputs from a designer to generate a piping model, and thus it takes much time for the designer to perform such task. Moreover, the piping model has no relation with that of hull structure. Thus, it is time-consuming and requires much effort if design changes arise. In this study, a method that generates quickly many pipes using a pipe tray and a conversion method that converts automatically the pipes into objects related with the hull structure are proposed. A piping modeling system based on the proposed methods is developed. The applicability of the developed system is demonstrated by applying it to the generation of the piping model of a deadweight 300,000ton VLCC(Very Large Crude oil Carrier). The results show that the developed system can quickly generate the piping model in relation with the hull structure.

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
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    • v.2 no.4
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    • pp.583-588
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    • 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.

Vibraiton and Power Flow Analysis for the Branched Piping System by Wave Approach (파동접근법을 이용한 분기된 배관계의 진동 및 파워흐름해석)

  • Koo, Gyeong-Hoe;Park, Yun-Sik
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.20 no.4
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    • pp.1225-1232
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    • 1996
  • In this paper the vibration and power flow analysis for the branched piping system conveying fluid are performed by wave approach. The uniform straight pipe element conveying fluid is formulated using the dynamic stiffness matrix by wave approach. The branched piping system conveying fluid can be easily formulated with considering of simple assumptions of displacements at the junction and continuity conditions of the pipe internal flow. The dynamic stiffness matrix for each uniform straight pipe element can be assembled by using the global assembly technique using in conventional finite element method. The computational method proposed in this paper can easily calculate the forced responses and power flow of the branched piping system conveying fluid regardless of finite element size and modal properties.

Design of type 316L stainless steel 700 ℃ high-temperature piping

  • Hyeong-Yeon Lee;Hyeonil Kim;Jaehyuk Eoh
    • Nuclear Engineering and Technology
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    • v.55 no.10
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    • pp.3581-3590
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    • 2023
  • High-temperature design evaluations were conducted on Type 316L stainless steel piping for a 700 ℃ large-capacity thermal energy storage verification test loop (TESET) under construction at KAERI. The hot leg piping with sodium coolant at 700 ℃ connects the main components of the loop heater, hot storage tank, and air-to-sodium heat exchanger. Currently, the design rules of ASME B31.1 and RCC-MRx provide design procedures for high-temperature piping in the creep range for Type 316L stainless steel. However, the design material properties around 700 ℃ are not available in those rules. Therefore, a number of material tests, including creep tests at various temperatures, were conducted to determine the insufficient material properties and relevant design coefficients so that high-temperature design on the 700 ℃ piping may be possible. It was shown that Type 316L stainless steel can be used in a 700 ℃ high-temperature piping system of Generation IV reactor systems or a renewable energy systems, such as thermal energy storage systems, for a limited operation time.

Dynamic Stability and Response Analysis of Piping System with Internal Flow (내부에 유체가 흐르는 파이프계의 동적안정성 및 응답해석)

  • 이우식;박철희;홍성철
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.15 no.6
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    • pp.1861-1871
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    • 1991
  • In this study, the piping system conveying unsteady flow is considered. The effects of coupling between the pipe motion and the velocity and pressure of fluid are included for the dynamic stability and response analysis of the piping system. The dynamic equations for a piping system are derived by Newtonian dynamics. For the momentum and continuity equations, the concept of moving control volume is applied. Thus, the governing equations derived herein are valid for the applications to the vibration problems occurred when a piping system starts up or shuts down and also when the valves and pumps operate. For a simply supported straight pipe, the stability analysis is conducted for various nondimensional parameters. The dynamic responses, in both stable and unstable region of stability chart, are numerically tested by the use of central difference method.

Analysis of Pressure Drop Characteristics for the Air-Particle Flow in Powder Transport Piping System (입자수송시스템 내 공기-입자 유동장의 압력손실 특성 해석)

  • Lee, Jae-Keun;Ku, Jae-Hyun;Kwon, Soon-Hong
    • The KSFM Journal of Fluid Machinery
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    • v.5 no.1 s.14
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    • pp.20-26
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    • 2002
  • This study reports the analysis of the pressure drop characteristics for the air-particle flow in powder transport piping system. The pressure drop characteristics of air-particle flow in piping system is not well understood due to the complexity of particles motion mechanism. Particles or powders suspended in air flow cause the increase of the pressure drop and affect directly the transportation efficiency. In this study, the pressure drop in powder transport piping system with straight and curved pipes is analyzed for the interactions of air flow and particle motion. The total pressure drop increases with increasing of the pipe length, the mixture ratio, and the friction factor of particles due to the increasing friction loss by air and particles in a coal piping system. For the coal powders of $74{\mu}m$ size and powder-to-air mass mixture ratio of 0.667, the total pressure drop by the consideration of powders and air flow is $30\%$ higher than that of air flow only.