• Title, Summary, Keyword: Burst Test

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Burst Behavior of Wear Scar of Steam Generators Tubes (증기발생기 전열관 마모 파열 거동)

  • Kim, Hong-deok
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.6 no.2
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    • pp.1-8
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    • 2010
  • Nuclear steam generator tubes have experienced wear degradation at tube support structure. Morphology of wear scar was analyzed by using eddy current signal. A burst test facility for steam generator tubes was established and tubes with 3 types of defects were tested. The burst test results show that the depth of wear scar is the main factor influencing the burst pressure of tubes, meanwhile, both the longitudinal length and the angle also have effect on the burst pressure. Based on test results, the burst pressure equation for wear degradation was proposed.

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Effect of External Pressure on the Burst Strength of Steam Generator Tube (증기발생기 전열관의 파열강도에 미치는 외압의 영향)

  • Cho, Sung-Keun;Bae, Bong-Kook;Seok, Chang-Sung
    • Proceedings of the KSME Conference
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    • pp.353-358
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    • 2004
  • Tracing the study of the burst test of steam generator tube, few studies have been reported to effect of external pressure acting on secondary-side in service condition. In this study the burst tests of Inconel 690TT were conducted in order to evaluate burst strength characteristics under the effect of external pressure. We obtained the result that the burst strength of Inconel 690TT increased when external pressure increased while both total circumferential elongation and uniform burst elongation were not affected. Also, according to the increased of external pressure, the size of the burst opening became smaller and the tear was getting severe.

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Burst Behavior for Mechanically Machined Axial Flaws of Steam Generator Tubings

  • Hwang, Seong Sik;Kim, Hong Pyo;Kim, Joung Soo
    • Corrosion Science and Technology
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    • v.3 no.1
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    • pp.30-33
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    • 2004
  • It has been reported that some events of a rupture of seam generator tube have occurred in nuclear power plants around the world. Main causes of the leakage are from various types of corrosion in the steam generator(SG) tubings. Primary water stress corrosion cracking(PWSCC) of steam generator tubings have occurred in many tubes in Korean plant, and they were repaired using sleeves or plugs, In order to develop proper repair criteria, it is necessary to ascertain the leak behavior of the tubings. A high pressure leak and burst testing system was manufactured. Various types of Electro Discharged Machined (EDM) notches were developed on the SG tubes. Leak rate and burst pressure were measured on the tubes at room temperature. Burst pressure of the part through wall defected tubes depends on the defect depth, Water flow rates after the burst were independent of the t1aw types; tubes having 20 to 60 mm long EDM notches showed similar flow rates regardless of the defect depth. A fast pressurization rate gave the tube a lower burst pressure than the case of a slow pressurization.

An Empirical Study on the Designed Burst Pressure of Type3 Composite Cylinder (Type3 복합용기 설계 파열압에 관한 실증연구)

  • Kim, ChangJong;Cho, Sung Min;Kim, Eun Jung;Yoon, Kee Bong
    • Journal of the Korean Institute of Gas
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    • v.17 no.3
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    • pp.20-26
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    • 2013
  • In this research, an empirical study on the designed burst pressure of Type3 composite cylinder was performed by hydrostatic burst test equipment. The designed burst pressure of Type3 composite cylinders, which are 6.8 liter and 31 MPa of service pressure, was estimated with the analysis using the finite element method. In order to confirm its accuracy, the burst test of small Type3 composite cylinders was perfomed through three times. The burst test equipment can pressurize to 400 MPa. As a result of comparison between the designed burst pressure and actual burst pressure, the difference was less than 4 percentage. With a test result, the analysis accuracy was verified. This technique will be applied to both qualification and inspection for the composite cylinder.

The Evaluation of the Creep Properties of ZIRLO Cladding Using the Ring Specimen (링 시험편을 이용한 ZIRLO 피복관의 크리프 특성 평가)

  • Bae, Bong-Kook;Koo, Jae-Mean;Seok, Chang-Sung
    • Proceedings of the KSME Conference
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    • pp.279-284
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    • 2004
  • In this study, we suggested the ring creep test using the ring specimen of Arsene for estimating the burst creep properties of the cladding in stead of burst creep test. For this objective, we used the load-displacement conversion relationship of ring specimen called LCRR which had been determined on our previous study at high temperature by performing the ring tensile test and the numerical analysis. Then we carried out both the ring creep test and the burst creep test between 350 $^{\circ}C$ and 600$^{\circ}C$ which were higher then the in-service temperature of the cladding in a reactor. The creep properties from the ring creep test with applying LCRR were compared with those from the burst creep test of closed-end specimens. From the results, it could be seen an very strong relationship between them, especially in Larson- Miller parameter. So, it is expected that we can easily anticipate the creep properties of not only claddings but also various small pressure pipes using the ring creep test.

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The Evaluation of the Creep Properties of ZIRLO Cladding Using the Ring Specimen (링 시험편을 이용한 ZIRLO 피복관의 크리프 특성 평가)

  • Bae Bong-Kook;Koo Jae-Mean;Seok Chang-Sung
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.29 no.7
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    • pp.964-969
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    • 2005
  • In this study, we suggested the ring creep test using the ring specimen of Arsene for estimating the burst creep properties of the cladding in stead of burst creep test. For this objective, we used the load-displacement conversion relationship of ring specimen called LCRR which had been determined on our previous study at high temperature by performing the ring tensile test and the numerical analysis. Then we carried out both the ring creep test and the burst creep test between $350^{\circ}C$ and $600^{\circ}C$ which were higher than the in-service temperature of the cladding in a reactor. The creep properties from the ring creep test with applying LCRR were compared with those from the burst creep test of closed-end specimens. From the results, it could be seen an very strong relationship between them, especially in Larson-Miller parameter. So, it is expected that we can easily predict the creep properties of not only claddings but also various small pressure pipes using the ring creep test.

The Evaluation of Burst Pressure for Corroded Pipeline by Full Scale Burst Test (실배관 파열시험을 통한 부식배관의 파열압력 평가)

  • Kim, Yeong-Pyo;Baek, Jong-Hyeon;Kim, U-Sik;Go, Yeong-Tae
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.26 no.1
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    • pp.203-210
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    • 2002
  • The transmission pipeline industry spends many millions of dollars annually performing inline inspections, excavating sites of possible corrosion, and repairing or replacing damaged sections of pipe. New criteria fur evaluation of the integrity of corroded pipe have been developed in recent years to help in controlling these costs. These new criteria vary widely in their estimates of integrity and the most appropriate criterion fur a given pipeline is net always clear. This paper presents an overview, comparison and evaluation of acceptability criteria for corrosion deflects in pipelines. By full scale burst tests, this paper has assessed the relative accuracy of each of theses criteria in predicting burst pressure. Many of the criteria appear to be excessively conservative and indicate that deflects must be repaired when none is needed, based upon burst test data.

The Evaluation of Burst Pressure for Corroded Weld in Gas Pipeline (가스배관 용접부위 부식에 대한 파열압력 평가)

  • Kim, Young-Pyo;Kim, Woo-Sik;Lee, Young-Kwang;Oh, Kyu-Hwan
    • Proceedings of the KSME Conference
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    • pp.222-227
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    • 2004
  • The failure assessment for corroded pipeline has been considered with the full scale burst test and the finite element analysis. The burst tests were conducted on 762 mm diameter, 17.5 mm wall thickness and API 5L X65 pipe that contained specially manufactured rectangular corrosion defect. The failure pressure for corroded pipeline was measured by burst testing and classified with respect to corrosion sizes and corroded regions - the body, the girth weld and the seam weld of pipe. Finite element analysis was carried out to derive failure criteria of corrosion defect on the pipe. A series of finite element analyses were performed to obtain a limit load solution for corrosion defects on the basis of burst test. As a result, the criteria for failure assessment of corrosion defect within the body, the girth weld and the seam weld of API 5L X65 gas pipeline were proposed.

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Radiated Emission of Electrical Fast Transient/Burst Signal and Its Countermeasures (전기적으로 빠른 과도현상/버스트 신호의 복사방출과 대책)

  • Park, Soo Hoon;Kim, Dong Il;Park, Youn Joon;Nah, Seung Wook
    • The Journal of Korean Institute of Electromagnetic Engineering and Science
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    • v.27 no.3
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    • pp.291-298
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    • 2016
  • In this paper, we studied about the radiated emission of EFT(Electrical Fast Transient)/Burst signal, referenced IEC-61000-4-4 of the international EMC standard and its effect on EUT(Equipment Under the Test) when EFT/Burst signal (Conducted noise) induced on a power cable to EUT. Firstly, we set up test sample by the standard and +4 kV standard signal is induced by EFT/Burst signal generator with 1 m length power cable for 1 minute. Consequently, we found not only induced EFT/Burst signal along power line, but also directly radiated emission signal from EFT/Burst signal generator (Radiated emission noise of EFT/Burst). The radiated emission signal of EFT/Burst was 30 dB which is higher than limit of CISPR 22 which is international EMC standard. Moreover, we measured the electric field strength by changing distance from maximum radiated emission point to electric field strength tester. As a result, this electric field strength was 23 V/m which is higher than international EMC standard test level(CISPR 24). Therefore, it was confirmed that the probability of malfunction may be high when radiated emission of EFT/Burst noise exists near the EUT.

Burst Test of Volute Casings for Liquid Rocket Turbopump (액체로켓 터보펌프 벌류트 케이싱의 파열시험)

  • Yoon, Suk-Hwan;Jeon, Seong-Min;Kim, Jin-Han
    • The KSFM Journal of Fluid Machinery
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    • v.14 no.4
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    • pp.12-18
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    • 2011
  • Volute casings for liquid rocket turbopump are designed and evaluated in a structural point of view. At the design step 3D modeling and finite element analyses are conducted iteratively. During the step various loads such as internal pressure, casing stiffness and mounting forces are considered in the analyses, along with the weight minimization effort. After the design step volute casings are manufactured by metal casting process, and then they are subjected to burst test for structural verification. In the burst test strains at several points are measured and compared with predicted values.