• Title/Summary/Keyword: power integrity

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The Experimental Study on Seismic Capacity of 154 kV & 345 kV Main Transformer Bushings (154 kV 및 345 kV 주변압기 부싱의 내진성능 시험 연구)

  • Hwang, Kyeong Min;Ham, Kyung Won;Kim, Gyeong Hwan
    • Journal of the Earthquake Engineering Society of Korea
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    • v.22 no.2
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    • pp.87-94
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    • 2018
  • In this study, seismic performance of bushings and their connection parts was analyzed by performing shaking table tests for various types of bushings widely used as auxiliary equipment of main transformers in domestic substations. As a result of the seismic tests of five types of 154 kV bushings according to the manufacturers, all the bushings secured the structural integrity even at the acceleration of 1.4 g and it was found that leakage of insulating oil didn't occur. Also, the average acceleration amplification rate at the upper part of the bushings was about 2.5 to 3.0 times higher than the lower one. On the other hand, when a representative 345 kV bushing was subjected to the seismic test, the structural integrity was secured even at 1.0 g acceleration similar to the design earthquake load level, but in this test, leakage of insulating oil occurred. However, when a stiffener restricting the connection of the bushing is installed in the same 345 kV bushing, the displacement of the bushing connection is controlled and the stiffener prevent the oil from leaking even at the acceleration of the designed seismic level.

A New Proposal for the Allowable Local Thickness of Straight Pipes in ASME Code Case N-597-2 (ASME 코드 케이스 N-597-2의 직관 국부허용두께의 새로운 제안)

  • Park, Jai-Hak;Shin, Kyu-In;Park, Chi-Yong;Lee, Sung-Ho
    • Journal of the Korean Society of Safety
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    • v.22 no.1 s.79
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    • pp.13-18
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    • 2007
  • Structural integrity assessment of thin-walled pipes and pipe items has become one of the major issues in the nuclear power plant. ASME Section XI Code Case N-597-2 provides a criterion for acceptance of the pipes. But the code case has several limitations for application and sometimes gives too conservative or non-conservative results. So it is necessary to understand fully the technical bases of the code case. In the code case N-597, the allowable local thicknesses of thinned straight pipes are given for three different cases. Because of the different technical base, each case gives different thickness values and sometimes gives contradictory values. In this paper attempts were made in order to propose a unified rule for the allowable local thickness and in order to remove or relax the restrictions on the application of the code case. For this purpose elastic stress analyses were made using the finite element method and the stress results were examined. Based on the obtained bending stress results, a very simple procedure was proposed to obtain the consistent allowable local thickness for the thinned straight pipes.

Evaluation of Structural Integrity and Cooling Performance of 4250 kVA Power Transformer with ONAN Mode (ONAN 모드 4250kVA 변압기의 구조 건전성과 냉각 성능의 평가)

  • Yang, Chaofan;Kim, Seongik;Cho, Jong-Rae
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.20 no.7
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    • pp.48-57
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    • 2021
  • The main research content of this paper is to evaluate the structural integrity and the cooling performance of 4250 kVA power transformer with ONAN(Oil Natural and Air Natural) mode. The dynamic analysis is used to verify the structural safety of the transformer by seismic loading. The transformer structure is simplified and NX software is used to build a three-dimensional model, and ANSYS commercial software is used to calculate the stress and deformation by applying corresponding load. The analysis result was evaluated whether it satisfies the design requirements according to the IEEE Std 693 standard. In terms of thermal analysis to evaluate the cooling performance, the thermal physical model is used to calculate the heat exchange between the radiator and the tank in the steady state, and the result is input into the Fluent software to calculate the internal temperature field of the transformer tank, which reduces the calculation cost of thermal fluid. Comparing the simulated hot spot temperature and top oil temperature of the transformer with the calculation results of the IEC60076 classic model, it is found that the error is only 1.9%.

Study of Boiler Tube Micro Crack Detection Ability by Metal Magnetic Memory (금속 자기기억법 활용 보일러 튜브의 미소 결함 검출력 연구)

  • Jungseok, Seo;Joohong, Myong;Jiye, Bang;Gyejo, Jung
    • KEPCO Journal on Electric Power and Energy
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    • v.8 no.2
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    • pp.93-96
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    • 2022
  • The boiler tubes of thermal power plants are exposed to harsh environment of high temperature and high pressure, and the deterioration state of materials rapidly increases. In particular, parent material and welds of the materials used are subjected to a temperature change and various constraints, resulting in deformation and its growth, resulting in frequent leakage accidents caused by tube failure. The power plant checks the integrity of boiler tubes through non-destructive testing as it may act as huge costs loss and limitation of power supply during power station shutdown period due to boiler tube leakage. However, the current non-destructive testing is extremely limited in the field to detect micro cracks. In this study, the ability of metal magnetic memory technique to detect flaws of size that are difficult to inspect by the visual or general non-destructive methods was verified in the early stage of their occurrence.

A Study on Quantitative Flaw Evaluation of Nuclear Power Plant Steam Generator Tube by Ultrasonic Testing (초음파를 이용한 원자력발전소 증기발생기 전열관의 정략적 결함 평가에 관한 연구)

  • Yoon, Byung-Sik;Kim, Yong-Sik;Lee, Hee-Jong;Lee, Yong-Ho
    • Journal of the Korean Society for Nondestructive Testing
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    • v.26 no.1
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    • pp.12-17
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    • 2006
  • A steam generator of nuclear power plant has thousands of thin tubes. These tubes play an important role in maintaining the pressure boundary between the primary and secondary side of nuclear power plant. The steam generator tube is easy to be damaged because of the severe operating conditions such as the high temperature and pressure. Therefore, tremendous efforts are made to assess the structural integrity of the steam generator tubes. The eddy current test is the most popular non-destructive test to assess the integrity of the tubes. However, the eddy current test has the limitation to size the flaw accurately because the eddy current signal behavior depends on the total volume of flaw. This paper shows the possibility that the ultrasonic test method can be applied to detect the flaws in the steam generator tubes and to measure them quantitatively. From the test results, it is expected that if the ultrasonic test is put to practical use in the steam generator tube inspection, the inspection results will be improved.

Conceptual Designs and Evaluation of the Treatment Process of Square and Cylindrical Concrete Re-Package Drums

  • Young Hwan Hwang;Sunghoon Hong;Seong-Sik Shin;Seokju Hwang;Jung-Kwon Son;Cheon-Woo Kim;Changgyu Kim;Kwang Soo Park;Taeseob Lim;Donghun Park
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.22 no.2
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    • pp.227-235
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    • 2024
  • After the permanent shut down of Kori Unit 1, various decommissioning activities will be implemented, including decontamination, segmentation, waste management, and site restoration. During the decommissioning period, waste management is among the most important activities to ensure that the process proceeds smoothly and within the expected timeframe. Furthermore, the radioactive waste generated during the operation should be sent to a disposal facility to complete the decommissioning project. Square and cylindrical concrete re-package drums were generated during the 1980s and 1990s. The square, containing boron concentrates, and cylindrical, containing spent resin, concrete re-package drums have been stored in a radioactive waste storage building. Homogeneous radioactive waste, including boron concentrates, spent resin, and sludge, should be solidified or packaged in high-integrity containers (HICs). This study investigates the sequential segmentation process for the separation of contaminated and non-contaminated regions, the re-packaging process of segmented or crushed cement-solidified boron concentrate, and re-packaging in HICs. The conceptual design evaluates the re-packaging plan for the segmented and crushed cement-solidified waste using HICs, which is acceptable in a disposal facility, and the quantity of generated HICs from the treatment process.

Schemes to enhance the integrity of P91 steel reheat steam pipe of a high-temperature thermal plant (고온 화력 P91강 재열증기배관의 건전성 제고 방안)

  • Lee, Hyeong-Yeon;Lee, Jewhan;Choi, Hyun-Sun
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.16 no.1
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    • pp.74-83
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    • 2020
  • A number of so-called 'Type IV' cracking was reported to occur at the welded joints of the P91 steel or P92 steel reheat steam piping systems in Korean supercritical thermal power plants. The reheat steam piping systems are subjected to severe thermal and pressure loading conditions of coolant higher than 570℃ and 4MPa, respectively. In this study, piping analyses and design evaluations were conducted for the piping system of a specific thermal plant in Korea and suggestions were made how structural integrity could be improved so that type IV cracks at the welded joints could be prevented. Integrity evaluations were conducted as per ASME B31.1 code with implicit consideration of creep effects which was used in original design of the piping system and as per nuclear-grade RCC-MRx code with explicit consideration of creep effects. Comparisons were made between the evaluation results from the two design rules. Another approach with modification or reduction of the redundant supports in the piping systems was investigated as a tool to mitigate thermal stresses which should essentially contribute to prevention of Type IV cracking without major modification of the existing piping systems. In addition, a post weld heat treatment method and repair weld method which could improve integrity of the welded joint of P91 steel were investigated.

Factors Influencing Compliance of Patient Role Behavior in Elderly Patients Receiving Hemodialysis (혈액투석을 받는 노인 환자의 환자역할행위이행에 영향을 미치는 요인)

  • Heo, Young-Kyu;Lee, Hyun-Ju
    • Journal of muscle and joint health
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    • v.30 no.3
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    • pp.157-167
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    • 2023
  • Purpose: The purpose of this study was to measure the relationship among activities of daily living, ego integrity, social support and the compliance of patient-role behavior in elderly patients receiving hemodialysis, including the effect of these variables on the compliance of patient-role behavior. Methods: A descriptive survey was conducted with 150 elderly patients over 65 years of age who were also receiving hemodialysis. Data was collected from September 28 to November 13, 2021 and analyzed using t-test, one-way ANOVA, Pearson's correlation coefficients, and multiple regression analysis with SPSS/WIN 26.0. Results: The results show that patient compliance had significant correlations with ego integrity (r=.63, p<.001) and social support (r=.28, p=.001). The other factors influencing patient compliance were the sub-domains of ego integrity, such as the acceptance of the past and the presence (β=.46, p<.001) and attitudes toward life (β=.26 p<.001), with an explanatory power of approximately 35.0% (F=17.21, p<.001). Conclusion: This study confirms that the ego integrity of elderly patients receiving hemodialysis has an effect on the compliance of patient role behavior. Nursing intervention programs that improve the ego integrity of elderly hemodialysis patients could help improve the compliance of patient-role behavior, which is an important factor in the disease management process.

Design and Implementation of e2eECC for Automotive On-Chip Bus Data Integrity (차량용 온칩 버스의 데이터 무결성을 위한 종단간 에러 정정 코드(e2eECC)의 설계 및 구현)

  • Eunbae Gil;Chan Park;Juho Kim;Joonho Chung;Joosock Lee;Seongsoo Lee
    • Journal of IKEEE
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    • v.28 no.1
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    • pp.116-122
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    • 2024
  • AMBA AHB-Lite bus is widely used in on-chip bus protocol for low-power and cost-effective SoC. However, it lacks built-in error detection and correction for end-to-end data integrity. This can lead to data corruption and system instability, particularly in harsh environments like automotive applications. To mitigate this problem, this paper proposes the application of SEC-DED (Single Error Correction-Double Error Detection) to AMBA AHB-Lite bus. It aims not only to detect errors in real-time but also to correct them, thereby enhancing end-to-end data integrity. Simulation results demonstrate real-time error detection and correction when errors occur, which bolsters end-to-end data integrity of automotive on-chip bus.

Structural Integrity Assessment of High-Strength Anchor Bolt in Nuclear Power Plant based on Fracture Mechanics Concept (원자력발전소 고강도 앵커 볼트의 파괴역학적 건전성평가)

  • Lim, Eun-Mo;Huh, Nam-Su;Shim, Hee-Jin;Oh, Chang-Kyun;Kim, Hyun-Su
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.7
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    • pp.875-881
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    • 2013
  • The failure of a bolted joint owing to stress corrosion cracking (SCC) has been considered one of the most important structural integrity issues in a nuclear power plant. In this study, the failure possibility of bolting, which is used to support the steam generator of a pressurized water reactor, owing to SCC and brittle fracture was evaluated in accordance with guidelines proposed by the Electric Power Research Institute, which are called the Reference Flaw Factor method. For this evaluation, first, detailed finite element stress analyses were conducted to obtain the actual nominal stresses of bolting in which either service loads or bolt preloads were considered. Based on these nominal stresses, the structural integrity of bolting was addressed from the viewpoints of SCC and toughness. In addition, the accuracy of the EPRI Reference Flaw Factor for assessing bolting failure was investigated using finite element fracture mechanics analyses.