• Title/Summary/Keyword: Tubesheet

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A Study on the Explosive Plugging of A Repair for Defective Tube/Tubeplate on the Nuclear Steam Generator (원자력 증기발생기 결함 세관 보수용 폭발 Plugging에 관한 연구)

  • 이병일;심상한;강정윤;이상래
    • Explosives and Blasting
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    • v.17 no.4
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    • pp.18-31
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    • 1999
  • The explosive forming has been used for many year to expand tubes into tubesheets. this process has demonstrated ability to direct carefully the energy of an explosive to expand tubes into tubesheet holes without damaging the tubesheet and without causing the excessive cold work at the tube I.D. that is normally associated with mechanical expansion. The success of explosive tube expansion provided the background for the development of the explosive tube plug. The main results are as follows : (1) The optimum explosives and explosive qualities are PETN, RDX, HMS and about 18~31gr/ft of explosive plugging in nuclear steam generator. (2) Explosive plugging's thickness is 0.9~1.8mm. If groove of 0.4 mm formed in plug outside, For the hydraulic leakage is go up, explosive plugging of formed groove are applicate tube and tubrplate. (3) Sheath is designed on the polyethylene of low density, In thermal impact test of the $430^\circ{C}$, hydraulic leakage is $300kg/cm^2$. (4) About 10~60mm oxide inclusions are existed on the space of explosive plug and tube protect to the leakage.

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DEVELOPMENT OF A STEAM GENERATOR LANCING SYSTEM

  • Jeong Woo-Tae;Kim Seok-Tae;Hong Sung-Yull
    • Nuclear Engineering and Technology
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    • v.38 no.4
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    • pp.391-398
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    • 2006
  • It is recommended to clean steam generators of nuclear power plants during plant outages. Under normal operations, sludge is created and constantly accumulates in the steam generators. The constituents of this sludge are different depending on each power plant characteristics. The sludge of the Kori Unit 1 steam generator, far example, was found to be composed of 93% ferrous oxide, 3% carbon and 1% of silica oxide and nickel oxide each. The research to develop a lancing system that would remove sludge deposits from the tubesheet of a steam generator was started in 1998 by the Korea Electric Power Research Institute (KEPRI) of the Korea Electric Power Corporation (KEPCO). The first commercial domestic lancing system in Korea, the $KALANS^(R)-I$ Lancing System, was completed in 2000 for Kori Unit 1 for cleaning the tubesheet of its Westinghouse Delta-60 steam generator. Thereafter, the success of the development and site implementation of the $KALANS^(R)-I$ lancing system for YGN Units 1&2 and Ulchin Units 3&4 was also realized in 2004 for sludge removal at those sites. The upper bundle cleaning system for Westinghouse model F steam generators is now under development.

Yeonggwang #1/2 steam condenser leakage repair works (영광 #1/2 복수기 누수부 보수공사)

  • 이상철;공창식
    • Proceedings of the KWS Conference
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    • 2003.05a
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    • pp.117-119
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    • 2003
  • Power plant efficiency and availability depend greatly on condenser performance. However, during commissioning of Yeonggwang #1/2 steam condenser sodium leakage occurred, because of tube to tubesheet only roll expanding. Therefore this report is explaining that pre-test for the shake of improvement reliable repair processes & selected sampling tube re-expansion in-situ applications.

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A Brief Review on the Design Factors of Steam Generator U-Tube Assembly for CANDU Type Nuclear Power Plant

  • Park, Nam-Il;Park, June-Soo
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05d
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    • pp.321-326
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    • 1996
  • During the plant operation, steam generator U-tube assembly will potentially be subject to adverse environmental conditions which can cause damages to them. This report addresses the major design factors of CANDU type steam generator which are intended to minimize the potential tube damages. Such factors include U-tube material, high circulation ratio, tube-to-tubesheet joint, tube support design. Also a few suggestions are presented for the design and performance improvement of CANDU type steam generators.

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A Study on the Structural Integrity Considering the Installation of a Micro-tube Heat Exchanger (미세튜브 열교환기의 장착을 고려한 구조건전성에 관한 연구)

  • Oh, Se Yun;Kim, Tae Jin;Cho, Jong Rae;Jeong, Ho Sung
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.4
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    • pp.447-451
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    • 2015
  • The objective of this study is to predict the structural characteristics of a heat exchanger mounted on an aircraft engine using finite element analysis. The plastic fracture and life of the heat exchanger were estimated by a thermo-mechanical analysis. Tensile tests were conducted under high temperature conditions (700, 800, 900, 1000 K) using five specimens to obtain the mechanical properties of the Inconel 625 tubes. To assess the structural characteristics of the heat exchanger, the full and partial models were applied under the operating conditions given by the thermo-mechanical and inertial load. As a result, the case, tubesheet, flange, and mounting components have a reasonable safety margin to the allowable stress assuming a fatigue strength of Inconel 625 of 10000 cycles under 1000 K.

An Interaction Effect of Eddy Current Signals Due to the Neighboring Signal Sources (근접한 두 신호원에 의한 와전류 신호의 간섭 효과)

  • Cheong, Y.M.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.11 no.1
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    • pp.7-12
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    • 1991
  • The multi-frequency eddy current technique has been used for evaluation of various type of defects in tubings. However, this technique is not sufficient to detect and evaluate the defect in tubings if the defect is located in the geometrically complicated area(e. g. tube support plate, anti-vibration bar, tubesheet area) and mixing residue signal is significant to the defect signal. In order to improve the reliability of the multi-frequency eddy current technique, the effect of the interaction of mixing residue after frequency mixing with a function of distances between the defect and the tube support plate boundary has been analyzed theoretically. The experimental results have been discussed with the theoretical developments. The calculation shows the interaction between the two neighboring signal sources could be significant within the range of approximately 1.0mm with the experimental condition.

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A Study on the Tube/tubesheet Interface in the Heat Exchangers Jointed by Explosive Bonding (폭발접합된 열교환기류 튜브와 튜브시트의 계면 특성에 관한 고찰)

  • 이병일;공창식;이상철
    • Journal of Welding and Joining
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    • v.18 no.4
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    • pp.38-47
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    • 2000
  • Characteristics of the interface between tube and tube sheet which were formed by explosive expansion and roll expansion, have been studied in the research. The results are as follows: Optimum amounts of explosives for the expansion of Alloy 600 (19.05mm and 15.88mm) were found to be RDX 3.5-8.5g/m. Because explosive expansion caused les strain hardening and increased bounding strength, characteristics of the explosively expanded were better than those of mechanically expanded. As the transition region of the explosive expansion is inactive, the resistance to the stress corrosion cracking increases by 30∼40% compared to the roll and hydraulic expansion.

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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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Detectability and Sizing Ability of Rotating Pancake Coil Technique for Cracks in Steam Generator Tubes

  • Y. M. Cheong;K. W. Kang;Lee, Y. S.;T. E. Chung
    • Nuclear Engineering and Technology
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    • v.30 no.4
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    • pp.377-385
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    • 1998
  • Many nuclear power plants have experienced unscheduled shutdown due to the leakage of steam generator tubes. The leakages are normally due to the crack, possibly stress corrosion cracking (SCC) near the tube expansion at the top of tubesheet or at the tangential point of the row-1 U-bend region. The conventional eddy current technique, which makes use of a differential bobbin coil, has been found to be inadequate for the early detection of SCC. During the in-service inspection, therefore, it is a general practice that the rotating pancake coil (RPC) is used for detecting the cracks. Even in using RPC, however, it is difficult to determine the depth of the cracks quantitatively. This paper attempts to determine the detectability and sizing ability of RPC technique for axial or circumferential cracks at the tube expansion region. The simulated cracks with various dimensions were fabricated by electro-discharge machining (EDM) method. Experimental results are discussed with theoretical calculations.

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Development of Tube Quality Trend Analysis System using Non-Destructive Testing Information (비파괴검사정보를 활용한 Tube 건전성 추이분석 시스템 개발)

  • Shin, Jin-Ho;Song, Jae-Ju;Jang, Mun-Jong
    • Proceedings of the KIEE Conference
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    • 2001.10a
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    • pp.224-226
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    • 2001
  • 원자력발전소에서는 수많은 Tube로 구성된 증기발생기와 열교환기를 정기적으로 와전류를 이용하여 비파괴검사를 수행한다. 와전류는 재료의 재질, 결함, 이종금속, 형상변화 등에 의해 그 발생상태가 다르기 때문에 검출용 코일에서 얻어진 신호성분을 해석함으로써 재료의 비파괴검사가 가능하다. 본 논문에서는 비파괴검사정보를 추출하고 변환 처리하는 과정과 비파괴검사정보를 Tubesheet에 Mapping 처리하는 기능, 검사주기 및 기기별로 비파괴검사정보를 비교 분석할 수 있는 기능, 하나의 Tube에 대한 결함깊이별, 결함진폭별 결함성장률 현황 등 Tube의 건전성을 평가할 수 있는 추이분석 자료를 제공하는 시스템의 설계와 구현에 대한 개발 결과를 소개한다.

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