• Title/Summary/Keyword: 전열관

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Estimation of Flow-induced Vibration characteristics on Plugged Steam Generator (관막음된 증기발생기 전열관의 유체유발진동 특성 평가)

  • Cho, Bong-Ho;Ryu, Ki-Wahn;Park, Chi-Yong;Park, Su-Ki
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2002.11b
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    • pp.921-926
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    • 2002
  • In this study, we investigate the plugging effect on the CE type steam generator tube. The natural frequency and mode shape will be changed due to decrease of the effective mass distribution along the tube. We compared the variation of stability ratio for plugged tube with that for unplugged one. The natural frequency increased because of removing the cooling water inside the steam generator tube, but the stability ratio decreased inversely because of changing the vibrational model shape. We also investigated the turbulent excitation effect.

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Characteristics of Flow-induced Vibration for CE Type Steam Generator Tube with Various Column and Row Number (CE형 증기발생기 전열관의 행열 변화에 따른 유체유발진동 특성)

  • Ryu, Ki-Wahn;Cho, Bong-Ho;Park, Chi-Yong;Park, Su-Ki
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2002.11b
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    • pp.927-932
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    • 2002
  • The stability ratio and vibrational amplitude of each tube inside a steam generator have different values. We estimate the characteristics of flow-induced vibration for CE type steam generator with various column and row number of the tube. To obtain the thermal-hydraulic data and stability ratio we use the ATHOS3-MODI and PIAT-FEI/TE code respectively. It turns out that the steam generator has a bounded central zone with the distributed values of the stability ratio and the vibrational amplitude, and those values across the zone boundary become decreased.

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Burst pressure tests of axial part-through-wall steam generator tubes (증기발생기 축방향 부분관통균열 전열관의 파열 압력 시험)

  • Lee, Kuk-Hee;Kim, Hong-Deok;Kang, Yong-Seok;Nam, Min-Woo;Cho, Nam-Cheoul
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.10 no.1
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    • pp.56-63
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    • 2014
  • In this research, burst tests for axial notched steam generator tubes were conducted. To measure the burst pressure of notched tubes, a burst testing system was manufactured. The tests were conducted under internal pressure at room temperature. Part-through-wall and through-wall notches which have various geometries with different depths and lengths were machined by electro-discharged-machined(EDM) method. The burst pressure decreased exponentially with increasing notch length and decreased almost linearly with increasing notch depth. A comparison of the burst pressure with existing burst pressure solutions for cracked tube show that the existing solution agree well with the test results.

Influence on heat transfer due to uneven flow (유동 불균일이 전열관 튜브에 미치는 영향)

  • Chong, Chae-Hon;Song, Jung-Il
    • 한국태양에너지학회:학술대회논문집
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    • 2008.11a
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    • pp.273-279
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    • 2008
  • The purpose of this study is not only to evaluate thermal performance but also to find the stress behavior of heat transfer tubes under the part load operation in Heat Recovery Steam Generator. Flow analysis was performed to know the behavior of exhaust gas from gas turbine and thermal performance was calculated using distribution of hot exhaust velocity. In addition, tubes temperature during operation were gathered from actual plant to verify the uneven flow distribution under part load operation. Stress analysis was performed using tubes temperature data gathered from actual plant under both part and full load operations to know the stress behavior of tubes.

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Tube Plugging Criteria for the Non-Regenerative Heat Exchanger in the Steam Generator Blowdown System of Nuclear Power Plant (증기발생기 취출수계통 비재생열교환기 전열관 관막음 기준 설정)

  • Kim, Hyeong-Nam;Choe, Seong-Nam;Yu, Hyeon-Ju;Choe, Jin-Hyeok
    • Proceedings of the KWS Conference
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    • 2006.10a
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    • pp.38-40
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    • 2006
  • Nuclear power plants are urged to reduce operating and maintaining costs to remain competitive as well as to increase the safety preventing the radioactive material to the atmosphere. To reduce the cost and to increase the safety, the inspection of balance-of-plant heat exchanger becomes important. However, there are some problems for plugging the heat exchanger tubes since the criterion and its basis are not clearly described. The codes and standards related to show the tube plugging criteria may not exist currently. In this paper, a method to establish the tube plugging criteria of BOP heat exchangers is introduced and the tube plugging criteria for the non-regenerative heat exchanger in the steam generator blow-down system of nuclear power plant. This method relies on the similar method used to establish the plugging criteria for the steam generator tubes.

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Heat Transfer of Smooth and Finned Tubes in A CFBC (순환유동층 보일러 전열관의 열전달 특성)

  • Kim, Bu-Hyeon;Cho, Hyung-Hee
    • Proceedings of the KSME Conference
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    • 2000.11b
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    • pp.651-655
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    • 2000
  • The objective of present work is to investigate experimentally the characteristics of heat transfer. A fluidized bed combustion has advantages of pollution control, fuel flexibility and excellent heat transfer. The present study investigates fundamental phenomena of bed-to-surface heat transfer in high temperature fluidized beds to improve design of immersed tube surface. The tested operating variables are bed temperature, supeficial velocity, mean size of bed material, and the rake angle of fin. Generally, heat transfer rates between the fluidized bed and immersed finned-tube are much higher than those of a smooth tube. A life time of finned-tube is generally longer than that of smooth tube.

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Burst Pressure Evaluation for Through-Wall Cracked Tubes in the Steam Generator (관통균열이 존재하는 증기발생기 전열관의 파열압력 평가)

  • Kim, Hyun-Su;Kim, Jong-Sung;Jin, Tae-Eun;Kim, Hong-Deok;Chung, Han-Sup
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.7
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    • pp.1006-1013
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    • 2004
  • Operating experience of steam generators shows that the tubes are degraded by stress corrosion cracking, fretting wear and so on. These defected tubes could stay in service if it is proved that the tubes have sufficient structural margin to preclude the risk of tube bursting. This paper provides detailed plastic limit pressure solutions for through-wall cracks in the steam generator tubes. These are developed based on three dimensional(3D) finite element analyses assuming elastic-perfectly plastic material behavior. Both axial and circumferential through-wall cracks in free span and in u-bend regions are considered. The resulting limit pressure solutions are given in a polynomial form, and thus can be simply used in practical integrity assessment of the steam generator tubes.

Estimation of Flow-induced Vibration Characteristics on Plugged Steam Generator Tube (관막음된 증기발생기 전열관의 유체유발진동 특성 평가)

  • Cho, Bong-Ho;Ryu, Ki-Wahn;Park, Chi-Yong;Park, Su-Ki
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2002.11a
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    • pp.390.1-390
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    • 2002
  • In this study, we investigate the plugging effect on the CE type steam generator tube. The natural frequency and mode shape will be changed due to decrease of the effective mass distribution along the tube. We compared the variation of stability ratio for plugged tube with that fur unplugged one. The natural frequency increased because of removing the cooling water inside the steam generator tube, but the stability ratio decreased inversely because of changing the vibrational mode shape. We also investigated the turbulent excitation effect.

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Fracture Mechanics Analysis of the Steam Generator Tube after Shot Peeing (숏피닝 증기 발생기 전열관의 파괴역학적 해석)

  • Shin, Kyu-In;Park, Jai-Hak;Jhung, Myung-Jo;Choi, Young-Hwan
    • Proceedings of the KSME Conference
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    • 2003.11a
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    • pp.1180-1185
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    • 2003
  • One of the main degradation of steam generator tubes is stress corrosion cracking induced by residual stress. The resulting damages can cause tube bursting or leakage of the primary water which contained radioactivity. Primary water stress corrosion crack occurs at the location of tube/tubesheet hard rolled transition zone. In order to investigate the effect of shot peening on stress corrosion cracking, stress intensity factors are calculated for the crack which is located in the induced residual stress field.

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A Study on Distinguishing between Parent material and Weld ECT Signal at Seal Weld Zone for Steam Generator Tubing (증기발생기 전열관 밀봉용접부에서의 모재와 용접부 ECT 신호 구분에 관한 연구)

  • Cheon, Keun-Young;Shin, Ki-Seok;Nam, Min-Woo
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.1
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    • pp.25-32
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    • 2015
  • Many crack flaws have been detected at tubing seal weld zone in Steam Generator with Alloy600 material tubes. it is very difficult to discriminate the signal from parent material and that from weld zone because weld zone gives complicated ECT signal due to manufacturing processes. ECT signal analysis in the seal weld zone is very important since the tubes with crack in this area shall be out of service by plugging. The purpose of this paper is to distinguish between Parent material and Weld Zone ECT signal in the seal weld zone through the demonstration test of Steam Generator seal weld mock-up.