• Title/Summary/Keyword: LBB : 파단전누설

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Modification of Current Leak Before Break Criteria for Nuclear Piping System (원자력 발전소 배관에 대한 파단전누설 개념 적용기준의 수정)

  • Yu, Yeong-Jun;Kim, Yeong-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.20 no.6
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    • pp.1862-1871
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    • 1996
  • The puopose of this paper is sto modify the current LBB criteria. The validity of current LBB criteria and current standard LBB analysis mehtod are evaluated using linear elastic fracture mechanics and elastic-plastic fracture mechanics. The results of evaluation demonstrate that the current LBB driteria are very conservative and some level of margins already exist in the standard LBB analysis method. Thus, the margin on load .root. and margin on crack size 2 can be eliminated to extend LBB application for the samller diameter pipe.

원자력발전소 배관에 대한 파단전 누설개념 적용

  • 손갑헌;유영준
    • Journal of the KSME
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    • v.31 no.3
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    • pp.261-266
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    • 1991
  • 원자력발전소 배관에 대한 일반적인 파단전누설(LBB)개념 적용절차 및 해석 방법에 대해 간단히 기술하였다. 그러나 LBB해석방법은 배관의 크기 및 작용하중의 상태에 따라 많은 차이가 있 으므로 보다 많은 배관에 LBB개념을 적용하여 설계하기 위해서는 합리적인 해석방법의 마련, 배관재질의 파괴인성치 향상 및 원자력발전소의 운전조건 개선 등을 위한 계속적인 노력이 필요 하리라고 판단된다.

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파단전누설 설계를 위한 실배관 파괴저항시험

  • Seok, Chang-Seong
    • Journal of the KSME
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    • v.51 no.12
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    • pp.37-41
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    • 2011
  • 이 글에서는 원전배관의 안전설계 개념인 양단순간파단(DEGB: Double Ended Guillotine Break) 및 파단전누설(LBB: Leak Before Break)에 대해 설명하고, 파단전누설 설계를 위한 다양한 실배관 파과저항시험 방법 및 실배관 파괴저항시험의 필요성에 대해 소개하고자 한다.

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Leak-Before-Break (LBB) Assessment Method Considering Crack Nonlinearity Using Effective Elastic Modulus and Material Nonlinearity (유효탄성계수를 이용한 균열 비선형 및 재료 비선형을 고려한 파단전누설(LBB) 평가 방법)

  • Kim, Maan-Won;Kim, Sung-Hwan;Lee, Eui-Jong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.35 no.6
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    • pp.651-659
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    • 2011
  • With the increase in the thermal power output of recently developed nuclear power plants, the applied forces and moments are increased in some piping systems, so that the leak-before-break (LBB) application criteria would not be satisfied in those pipes. In this paper, we present a method for obtaining the additive LBB margin in the pipes by considering the nonlinearity of the crack and material properties. Finite element analysis and the moment-rotation equation of beam theory were used to calculate the nonlinearity of the crack and material properties. Moreover crack stability analysis was performed using the method proposed in this study. The LBB margin was increased effectively through consideration of the nonlinearity of the crack and material properties in the pipe.

Effect of Hydride of the PHWR Pressure Tube on the LBB Evaluation (중수로 압력관의 수화물이 LBB평가에 미치는 영향)

  • Oh, Dong-Joon;Kim, Young-Suk
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.5
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    • pp.610-616
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    • 2004
  • The aim of this study was to investigate the hydride embrittlement when the LBB evaluation was carried out for the integrity of PHWR Pressure Tubes. The transverse tensile and CCT toughness tests were performed at three hydrogen concentrations while the test temperatures were changed (RT to 30$0^{\circ}C$). Both the transverse tensile and the fracture toughness tests showed the hydrogen embitterment clearly at RT but this phenomenon was disappeared while the test temperature arrived at 25$0^{\circ}C$. Using the DHC test results, the CCL and LBB time were calculated and compared. The hydride embrittlement at the LBB evaluation made the LBB time short definedly. If the operating temperature, DHCV and LBB deterministic parameters such as A and m were known, LBB time could be estimated without the calculation of CCL.

Effect of Nozzle on LBB Evaluation for Small Diameter Nuclear Piping (직경이 작은 원자력배관의 파단전누설 해석에 미치는 노즐의 영향)

  • Yu, Yeong-Jun;Kim, Yeong-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.20 no.6
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    • pp.1872-1881
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    • 1996
  • LBB(Leak-Before-Break) analysis is performed for the highest stress location of each different type of mateerials in the nuclear piping line. In most cases, the highest stress occurs in the pipe and nozzle interface location. i.e. terminal end. The current finite element analysis approach utilizes the symmetry condition both for locations near the nozzle and for locationa away from the nozzle to minimize the size of the finite element model and to make analysis simple when calculating the J-integral values at the crack tip. In other words, the nozzle is not included in the finite element model. However, in reality, the symmetric condition is not applicable for the pipe-nozzle interface location. Because the pipe-nozzle interface location is asymmetric due to different stiffenss of the pipe and nozzle(both material and dimensions). The simplified analysis approach for pipe-nozzle interface locaiton is too conservative for a smaller diameter piping. In tlhis paper, various analyses are performed for the range of materials and crack sizes to evaluate the nozzle effect for a LBB anlaysis. This paper presents methodology for developing the piping evaluaiton diagram at the pipe-nozzle interface location.

Effect of Nozzle on Leak-Before-Break Analysis Result of Nuclear Piping (노즐이 원자력 배관의 파단전누설 해석 결과에 미치는 영향)

  • Kim, Yeong-Jin;Heo, Nam-Su;Gwak, Dong-Ok;Yu, Yeong-Jun;Pyo, Chang-Ryul
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.24 no.11
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    • pp.2796-2803
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    • 2000
  • For traditional Leak-Before-Break(LBB) analyses, symmetric conditions were assumed for a pipe-nozzle interface to simplify the analysis in calculating J-integral. However. this assumption could result in an overly conservative design criteria for a pipe-nozzle interface, Since the pipe-nozzle interface is asymmetric due to the difference of stiffness between pipe and nozzle, it is required to develop a new methodology considering the nozzle effect. The objective of this paper is to evaluate the effect of nozzle no the development of LBB design criteria for nuclear pipings. For this purpose, extensive finite element analysis were performed to evaluate the effect of nozzle on Crack Opening Area(COA), Detectable Leakage Crack(DLC) length and J-integral values. In conclusion, it was proven that the application of LBB concept could be extended for more nuclear piping system by considering the nozzle.

영광3,4호기 가압기 밀림관의 파단전 누설 설계(LBB) 타당성

  • 전재풍;정대율
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05b
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    • pp.753-760
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    • 1995
  • 본 보고서는 영광 3,4호기 가압기 밀림관(Surge Line)에 대한 파단전누설(Leak Before Break) 개념의 적용방법, 해석절차 및 해석결과에 대하여 기술하고 있다. 영광 3,4호기 가압기 밀림관에 대한 파단전누설해석은 배관계에 대한 정적, 동적 배관해석 결과를 토대로 큰 응력 값이 작용하는 부분에 대하여 수행하였다. 가상균열의 크기는 정상운전상태에서의 하중을 이용하여 결정하였으며 격납용기에 설치된 누설감지장치의 감지능력을 1.0gpm으로 가정하였다. 영광 3,4호기 가압기 밀림관에 대한 파단전 누설해석은 NUREG 1061,Vol.3 및 SRP3.6.3에 근거하여 수행하였으며 해석결과는 동 자료에서 제시하고 있는 적용기준을 만족하고 있는 것으로 평가되었다.

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Leak-Before-Break Assessment Margin Analysis of Improved SA508-Gr.1a Pipe Material (개선된 SA508-Gr.1a 배관재의 파단전누설평가 여유도 분석)

  • Kim, Maan-Won;Lee, Yo-Seob;Shin, In-Whan;Yang, Jun-Seog;Kim, Hong-Deok
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.16 no.1
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    • pp.42-48
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    • 2020
  • The effect of improving the tensile and J-R fracture toughness properties of SA508 Gr.1a on the LBB margin for the main steam pipe is investigated. The material properties and microstructure images of the existing main steam piping material SA106 Gr.C used in domestic nuclear power plants and the newly selected material SA508 Gr.1a were compared. For each material, LBB margins were calculated and compared through finite element analysis and crack instability evaluation. The LBB margin of the improved SA508 Gr.1a is found to be greatly improved compared to that of the existing SA106 Gr.C and SA508 Gr.1a. This is because of the increased material's strength and J-R fracture toughness compared to the previous materials. In order to analyze the effect of physical property change on the LBB margin, the sensitivity of each LBB margin according to the variation of tensile strength and J-R fracture toughness was analyzed. The effect of the change in tensile strength was found to be greater than that of the change in fracture toughness. Therefore, an increase in strength significantly influenced the improvement of the LBB margin of the improved SA508 Gr.1a.

유한요소의 형태 및 경계 조건이 Applied J 적분값에 미치는 영향

  • 라인식;조인득;지계광
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05c
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    • pp.123-130
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    • 1996
  • 탄소성파괴역학의 발달과 함께 원자력 발전소의 설계시 고려해야 하는 고에너지 배관의 양단파단사고와 같은 극한 가정 대신 파단전누설(LBB : Leak Before Break)개념을 배관설계시 고려할 수 있도록 관련 규제 요건이 완화되어 원자력 발전소 고에너지 계통 설계에 새로운 설계 개념으로 적용할 수 있게 되었다. 파단전누설개념 적용시 균열 안정성 평가에 가장 널리 사용되는 방법은 J-T 방법이다. 본 연구에서는 유한요소법 사용시 균열 선단에서 요소의 크기 및 경계 조건 (Boundary Condition)이 변화할 때 Applied J 적분값에 미치는 영향을 ABAQUS 전산 프로그램을 이용하여 조사하였다.

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