• Title/Summary/Keyword: SG Tube

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Prediction of Defect Size of Steam Generator Tube in Nuclear Power Plant Using Neural Network (신경회로망을 이용한 원전SG 세관 결함크기 예측)

  • Han, Ki-Won;Jo, Nam-Hoon;Lee, Hyang-Beom
    • Journal of the Korean Society for Nondestructive Testing
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    • v.27 no.5
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    • pp.383-392
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    • 2007
  • In this paper, we study the prediction of depth and width of a defect in steam generator tube in nuclear power plant using neural network. To this end, we first generate eddy current testing (ECT) signals for 4 defect patterns of SG tube: I-In type, I-Out type, V-In type, and V-Out type. In particular, we generate 400 ECT signals for various widths and depths for each defect type by the numerical analysis program based on finite element modeling. From those generated ECT signals, we extract new feature vectors for the prediction of defect size, which include the angle between the two points where the maximum impedance and half the maximum impedance are achieved. Using the extracted feature vector, multi-layer perceptron with one hidden layer is used to predict the size of defects. Through the computer simulation study, it is shown that the proposed method achieves decent prediction performance in terms of maximum error and mean absolute percentage error (MAPE).

Development of ETSS for the SG Secondary Side Loose Part Signal Detection and Characterization (SG전열관 2차측 이물질 검출 및 특성분석을 위한 ETSS 개발)

  • Shin, Ki Seok;Moon, Yong Sig;Min, Kyong Mahn
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.7 no.3
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    • pp.61-66
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    • 2011
  • The integrity of the SG(Steam Generator) tubes has been challenged by numerous factors such as flaws, operation, atmosphere, inherently degraded materials, loose parts and even human errors. Of the factors, loose parts(or foreign materials) on the secondary side of the tubes can bring about volumetric defects and even leakage from the primary to the secondary side in a short period of time. More serious concerns about the loose parts are their unknown influx path and rapid growth rate of the defects affected by the loose parts. Therefore it is imperative to detect and characterize the foreign materials and the defects. As a part of the measures for loose part detection, TTS(Top of Tubesheet) MRPC(Motorized Rotating Pancake Coils) ECT has been carried out especially to the restricted high probability area of the loose part. However, in the presence of loose parts in the other areas, wide range loose part detection techniques are required. In this study, loose part standard tube was presented as a way to accurately detect and characterize loose part signals. And the SG tube ECT bobbin coil and MRPC ISI(In-service Inspection) data of domestic OPR-1000 and Westinghouse Model F(W_F) were reviewed and consequently, comprehensive loose part detection technique is derived especially by applying bobbin coil signals

WEAR BEHAVIOUR OF STEAM GENERATOR TUBES IN ROOM TEMPERATURE WATER

  • Lee, Young-Ho;Kim, Hyung-Kyu;Kim, In-Sup
    • Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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    • 2002.10b
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    • pp.203-204
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    • 2002
  • The wear behaviour of steam generator (SG) tubes (Inconel 600 and 690) against support materials (405 and 409 ferritic stainless steels) has been experimentally studied in room temperature water using reciprocating wear apparatus with tube-an-plate configuration. The results showed that the wear rate of Inconel 690 was lower than that of lnconel 600 with increasing normal loads and sliding amplitudes. Also, plastic deformation layers appear below the surface of both SG tubes, which have a specific thickness and are small compared with their grain size. This means that wear rate of SG tubes in water condition is closely related to the formation and fracture of plastic deformation layers.

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Steady-State Performance Analysis of Pressurizer and Helical Steam Generator for SMART

  • Seo, Jae-Kwang;Kang, Hyung-Seok;Kim, Hwan-Yeol;Cho, Bong-Hyun;Lee, Doo-Jeong
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.310-315
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    • 1997
  • System-Integrated Modular Advanced Reactor (SMART), where major primary components such as modular helical steam generator and self regulating pressurizer are integrated into reactor vessel, is currently under development. The pressurizer is designed to control the primary pressure mainly with partial pressure of nitrogen gas and to maintain the fluid temperature as low as possible for the purpose of minimizing steam contribution. The steam generator (SG) is designed to produce super-heated steam inside tube at power operation. Because the in-vessel pressurizer and in-vessel SG are classified as the characteristic components of SMART, it is important to perform a steady state calculation of these components in order to evaluate the adoption of these components. A steady state analysis of the in-vessel pressurizer and in-vessel SG has been performed under normal power operation and the results show an acceptable performance of the components.

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Defect Signal Analysis of Steam Generator Tube in NPP Using ECT Array Probe (ECT Array Probe를 이용한 원전 SG세관의 결함 신호해석)

  • Lim, Geon-Gyu;Kim, Ji-Ho;Lee, Hyang-Beom
    • Proceedings of the KIEE Conference
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    • 2008.07a
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    • pp.772-773
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    • 2008
  • 본 논문에서는 ECT Array Probe를 이용한 원자력 발전소의 SG세관의 결함 신호를 해석하였다. 프로브의 전자기적 특성을 해석하기 위하여 맥스웰 방정식을 이용하여 지배방정식을 유도하였고, 3차원 유한요소법을 이용하여 전자기 수치 해석을 수행하였다. 신호해석을 위해 사용된 결함의 종류는 FBH결함이며, 결함의 깊이는 세관 두께의 40[%] 및 100[%]로 하였다. 시험주파수는 300[kHz], 400[kHz]를 사용하였으며, 각각의 시험주파수에 대한 결과를 비교 분석하였다. 해석결과 결함부위에서 신호의 증가를 확인할 수 있었으며, 주파수 시험변화시 300[kHz]보다 400[kHz]일때 결함 신호가 증가하는 것을 확인할 수 있었다. 또한 획득한 신호를 ASME 표준 시험편을 이용한 ECT Array Probe의 와전류탐상 실험신호와 비교하였다. 본 논문의 결과는 ECT Array Probe를 이용하여 원전 SG세관 검사시 결함신호해석에 도움이 될 것으로 사료된다.

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The Design Optimization of Preventive Measure Against APR1400 Steam Generator Tube Fretting Wear (신형경수로 증기발생기 마모손상 억제를 위한 설계최적화)

  • Lim, Hyuk-Soon;Park, Young-Sheop;Lee, Kwang-Han;Lee, Seok-Ho;Chung, Dae-Yul
    • Proceedings of the KSME Conference
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    • 2004.04a
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    • pp.2047-2052
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    • 2004
  • Inconel-600 alloy has been used as steam generator tube material for current pressurized water reactors (PWRs). The long-term operation of steam generators showed that the use of this material induced localized corrosion damages and increased tube wear of steam generator. To protect these problems, steam generator tube material is being changed to Inconel-690 alloy. Based on the current trend, we have chosen Inconel 690 as the Advanced Power Reactor 1400 (APR1400) steam generator(SG) tube material and performed the design optimization of preventive measure against tube fretting wear for the APR1400 steam generator. In this paper, we examined the technical consideration in this modification : the selection of material, wear characteristics, effect of the Egg-crate Flow Distribution Plate installation, and effect analysis of vertical strip installation.

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Simulation and Analysis of ECT Signals Obtained at Tubesheet and Tube Expansion Area

  • Song, Sung-Chul;Lee, Yun-Tai;Jung, Hee-Sung;Shin, Young-Kil
    • Journal of the Korean Society for Nondestructive Testing
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    • v.26 no.3
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    • pp.174-180
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    • 2006
  • Steam generator (SG) tubes are expanded inside tubesheet holes by using explosive or hydraulic methods to be fixed in a tubesheet. In the tube expansion process, it is important to minimize the crevice gap between expanded tube and tube sheet. In this paper, absolute and differential signals are computed by a numerical method for several different locations of tube expansion inside and outside a tubesheet and signal variations due to tubesheet, tube expansion and operating frequencies are observed. Results show that low frequency is good for detecting tubesheet location in both types of signals and high frequency is suitable for sizing of tube diameter as well as the detection of transition region. Also learned is that the absolute signal is good for measuring tube diameter, while the differential signal is good for locating the top of tubesheet and both ends of the transition region. In the case of mingled anomaly with tube expansion and tubesheet, low frequency inspection is found to be useful to analyze the mixed signal.

Numerical Analysis of Added Mass Coefficient for Outer Tubes of Tube Bundle in a Circular Cylindrical Shell (원통 내부에 배열된 외곽 전열관의 유체 부가질량계수 해석)

  • Yang, Keum-Hee;Ryu, Ki-Wahn
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.26 no.2
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    • pp.203-209
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    • 2016
  • According to the wear detection history for the steam generator tubes in the nuclear power plant, the outer tubes inside the steam generator have more problems on the flow-induced vibration than inner tubes. Many researchers and engineers have used a specified added mass coefficient for a given tube array during the design stage of the steam generator even though the coefficient is not constant for entire tube in cylindrical shell. The aim of this study is to find out the distribution of added mass coefficients for each tube along the radial location. When numbers of tubes inside a cylindrical shell are increased, values of added mass coefficients are also increased. Added mass coefficients at outer tubes are less than those of inner tubes and they are decreased with increasing the gap between the outermost tube and the cylindrical shell. It also turns out when the gap between the outermost tube and the cylindrical shell approaches infinite value, the added mass coefficient converges to an asymptotic value of given tube array in a free fluid field.