• Title/Summary/Keyword: 파열균열

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복합 균열이 존재하는 증기 발생기 전열관에서의 파열 압력 해석

  • 신규인;박재학;김홍덕;정한섭
    • Proceedings of the Korean Institute of Industrial Safety Conference
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    • 2002.11a
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    • pp.13-18
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    • 2002
  • 증기 발생기 전열관의 파열 사고는 지난 20년 동안 2년마다 1개씩의 비율로 발생되어왔고 최근 몇 년간은 매년 발생되고 있는 추세이다(3). 전열관의 파열 사고는 응력부식균열, 피로 그리고 마멸 등의 원인에 의해서 발생되고 있는 것으로 알려져 있다. 초기 발전소에서 균열의 발생 및 성장은 축 방향 균열에 국한하여 관심을 가졌었으나 최근 원주 방향 균열에 의한 사고가 발생되면서 원주 방향 균열에 대해 관심을 가지게 되었다.(중략)

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Evaluation of Bursting Behavior in Anchorage Zone of PSC I Girders (PSC I 거더의 정착부 파열거동 평가)

  • Choi, Kyu Chon;Park, Young Ha;Paik, In Yeol
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.30 no.3A
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    • pp.329-336
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    • 2010
  • An experimental study to evaluate bursting behavior in anchorage zone of the standard PSC I girders (span length : 30 m) has been carried out. The arrangement of bursting reinforcement in anchorage zone of the standard PSC I girders is considered to be designed without accurately reflecting the stress flows in the end zone of the PSC I girders caused by presstressing forces of the tendons. Also, due to excessive arrangement of the bursting bars, the workability of the girder is decreased greatly. In this study, three specimens with the same dimensions as the end zone of the standard PSC I girder are prepared and the experiment is carried out by applying PS forces. The bursting reinforcement of each specimen consists of 100 mm, 200 mm, and 300mm spacings, respectively. The experimental results show that the range of the PS forces to cause crack in the anchorage zone of the specimen are more than 1.6 times of the design PS forces. The bursting cracks occur in the vertical direction on the inside of all specimens. After applying 2.7 times of the design PS force, some of the transverse bursting reinforcements only in the specimen reinforced by 300 mm spacing yielded. The experimental results show that the anchorage zone of the standard PSC I girders arranged by 300 mm spacing of the bursting reinforcements which is the maximum spacing allowed in the road bridge design specifications, can be considered safe enough.

Static Shear Resistance of Cast-In-Place Anchors in Cracked Concrete (균열콘크리트에 매입된 선설치앵커의 정적 전단하중에 대한 저항강도)

  • Park, Yong Myung;Ju, Ho Jung;Kim, Dong Hyun;Kang, Moon Ki;Lee, Jong Han
    • Journal of Korean Society of Steel Construction
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    • v.27 no.1
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    • pp.87-97
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    • 2015
  • In this study, an experimental study was performed to evaluate the concrete breakout strength of cast-in-place(CIP) anchors in cracked concrete under static shear loading. The CIP anchors involved in this study were 30mm in diameter with an edge distance of 150mm and an embedment length of 240mm. The experiment was carried out for two specimens in uncracked concrete and three specimens in cracked concrete orthogonal and parallel to the direction of shear loading, respectively. Compared to the uncracked concrete specimen, cracked specimen orthogonal to the direction of shear loading showed no reduction in the concrete breakout strength and that parallel to the load direction about 91% strength which corresponds to 84% of uncracked concrete strength defined in ACI 318-11. Therefore, the experimental results showed smaller decrease in the shear resistance of CIP anchors in cracked concrete than that specified in ACI code which account for 71% strength of uncracked concrete in cracked concrete.

Experimental and Analytical Study on Burst Pressure of a Steam Generator Tube with a T-type Combination Crack (T-형 복합 균열이 존재하는 증기발생기 전열관의 파열압력 시험 및 해석)

  • Shin, Kyu-In;Park, Jai-Hak;Kim, Hong-Deok;Chung, Han-Sub;Choi, Young-Hwan
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.2
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    • pp.158-164
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    • 2004
  • Steam generator tubes experience widespread degradations such as stress corrosion cracking, wear, tube rupture, denting, fatigue and so on. The resulting damages can cause tube bursting or leak of the primary water which contains radioactivity Therefore the allowable size of the damage is required to be determined on the maintenance purpose. The burst pressure of a tube with a T-type combination crack consisting of longitudinal and circumferential cracks is obtained experimentally and analytically. Fracture parameters such as stress intensity factor and crack opening angle are investigated. Also the burst pressure for a T-type combination crack is compared with that of a single longitudinal crack to develop a length-based criteria.

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.

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.

복합균열이 존재하는 증기 발생기 전열관의 파열압력해석

  • 신규인;박재학;김홍덕;정한섭
    • Proceedings of the Korean Institute of Industrial Safety Conference
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    • 2000.11a
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    • pp.257-262
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    • 2000
  • 원전을 가동함에 따라 전열관에서는 SCC(stress corrosion cracking), 프레팅(fretting) 등과 같은 다양한 종류의 결함이 발생된다. 이러한 결함이 발생된 전열관에 대해서는 건정성 평가를 수행하여 계속 가동을 수행하던가, 전열관 막음(plugging) 또는 재생보수(sleeve) 등의 보수 작업을 수행하게 된다. 현행 전열관의 구조 건정성 확보를 위한 방안 중의 하나로 결함의 종류, 위치 등에 관계없이 모든 결함에 대하여 40% 관두께 기준을 적용하고 있다[1]. 그러나 현재 적용되고 있는 40% 관두께 보수기준은 전열관의 파열사고 가능성을 완벽하게 차단하지 못하면서도 과도하게 보수적인 측면이 있다.(중략)

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손상된 파이프의 구조 안전성 평가

  • 박재학
    • Bulletin of the Korean Institute for Industrial Safety
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    • v.2 no.1
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    • pp.34-40
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    • 2002
  • 화학설비나 산업설비 또는 국가 기간 설비에서 파이프(pipe)는 중요한 위치를 차지하고 있으며 파이프의 파열은 그대로 대형 사고나 설비 가동의 중단으로 연결되는 경우가 많다. 따라서 파이프의 구조건전성을 유지하는 것은 안전의 확보와 생산 설비의 효율적 운용을 위하여 긴요하다. 파이프 재료 내부에는 재료 제작 시, 또는 파이프 제작 시 발생된 결함이나 사용 중 부식이나 피로 등의 영향으로 생성된 결함이 존재한다. 이러한 결함은 파이프의 강도를 낮추게 되고, 파이프의 잔류강도가 사용압력보다 낮아지게 되면 파이프가 파열하게 된다. 따라서 본 글에서는 파이프에 균열이 존재하거나 손상된 경우의 구조안전성 평가를 위하여 필요한 해석방법에 대하여 살펴본다.(중략)

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