• Title/Summary/Keyword: 파괴저항곡선 예측

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원자력 배관용 스테인레스강의 파괴저항곡선 예측

  • 장윤석;석창성;김영진
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05a
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    • pp.796-802
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    • 1995
  • 본 연구의 목적은 원자력 배관용 스테인레스강의 J-R곡선을 예측하기 위한 2가지 방법 올 제시하는 것이다. 첫 번째 방법에서는 균열길이/시편폭 비를 변수로 한 탄소성 유한요소해석을 수행하여 파괴변형률에 근거한 P-$\delta$곡선을 얻고, 이 결과로부터 일반궤적법을 응용하여 J-R곡선을 구하였다. 두 번째 방법에서는 $\sigma$-$\varepsilon$곡선과 J-R곡선의 상관관계를 통계처리하여 응력-변형률시험결과로부터 J-R곡선을 예측할 수 있는 실험식을 제시하였다. 본 연구에서 제시한 방법들을 이용하여 구한 예측결과는 실험결과와 대체로 잘 일치하였다.

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Prediction of Fracture Resistance Curves for Nuclear Piping Materials(III) (원자력 배관재료의 파괴저항곡선 예측)

  • Chang, Yoon-Suk;Seok, Chang-Sung;Kim, Young-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.21 no.11
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    • pp.1796-1808
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    • 1997
  • In order to perform leak-before-break design of nuclear piping systems and integrity evaluation of reactor vessels, full stress-strain curves and fracture resistance(J-R) curves are required. However it is time-consuming and expensive to obtain J-R curves experimentally. To resolve these problems, three different methods for predicting J-R curves from tensile data were proposed by the authors previously. The objective of this paper is to develop a computer program based on those J-R curve prediction methods. The program consists of two major parts ; the main program part for the J-R curve prediction and the database part. Several case studies were performed to verify the program, and it was shown that the predicted results were, in general, in good agreement with the experimental ones.

Estimation of the Fracture Resistance Curve for the Nuclear Piping Using the Standard Compact Tension Specimen (표준 CT시험편을 이용한 실배관 파괴저항 곡선 예측)

  • Park, Hong-Sun;Heo, Yong;Koo, Jae-Mean;Seok, Chang-Sung;Park, Jae-Sil;Cho, Sung-Keun
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.33 no.9
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    • pp.930-937
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    • 2009
  • The estimation method of the fracture resistance curve for the pipe specimen was proposed using the load ratio method for the standard specimen. For this, the calculation method of the load - CMOD curve for the pipe specimen with the common format equation(CFE) was proposed by using data of the CT specimen. The proposed method agreed well with experimental data. The J-integral value and the crack extension were calculated from the estimated load - CMOD data. The fracture resistance curve was estimated from the calculated J-integral and the crack extension. From these results, it have been seen that the proposed method is reliable to estimate the J-R curve of the pipe specimen.

Prediction of Fracture Resistance Curves for Nuclear Piping Materials (원자력 배관재료의 파괴저항곡선 예측)

  • 장윤석;석창성;김영진
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.19 no.4
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    • pp.1051-1061
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    • 1995
  • In order perform leak-before-break design of nuclear piping systems and integrity evaluation of reactor vessels, full stress-strain (.sigma. - .epsilon.) curves and fracture resistance (J-R) curves are required. However it is time-consuming and expensive to obtain J-R curves experimentally. The objective of this paper is to develop two methods for J-R curve prediction. In the first method, elastic-plastic finite element analyses for a series of crack length / specimen width ratio were performed. Accordingly the load versus load line displacement (P .delta.) curve corresponding to the fracture strain is obtained and the J-R curve based on the generalized locus method is obtained. In the second method, the correlation between .sigma.-.epsilon. curves and J-R curves was statistically analyzed and an empirical equation to predict the J-R curve from the .sigma.-.epsilon. test result is proposed. A good correlation between the predicted results based on the proposed methods and the experimental ones is obtained.

Prediction of Fracture Resistance Curves for Nuclear Piping Materials(II) (원자력 배관재료의 파괴저항곡선 예측)

  • Chang, Yoon-Suk;Seok, Chang-Sung;Kim, Young-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.21 no.11
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    • pp.1786-1795
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    • 1997
  • In order to perform leak-before-break design of nuclear piping systems and integrity evaluation of reactor vessels, full stress-strain curves and fracture resistance (J-R) curves are required. However it is time-consuming and expensive to obtain J-R curves experimentally. The objective of this paper is to modify two J-R curve prediction methods previously proposed by the authors and to propose an additional J-R curve prediction method for nuclear piping materials. In the first method which is based on the elastic-plastic finite element analysis, a blunting region handling procedure is added to the existing method. In the second method which is based on the empirical equation, a revised general equation is proposed to apply to both carbon steel and stainless steel. Finally, in the third method, both full stress-strain curve and finite element analysis results are used for J-R curve prediction. A good agreement between the predicted results based on the proposed methods and the experimental ones is obtained.

Estimation of Fracture Resistance Curves of Nuclear Materials Using Small Punch Specimen (소형펀치 시편을 이용한 원자력 재료의 파괴저항곡선 예측)

  • Chang, Yoon-Suk;Kim, Jong-Min;Choi, Jae-Boong;Kim, Min-Chul;Lee, Bong-Sang;Kim, Young-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.31 no.1 s.256
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    • pp.70-76
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    • 2007
  • Elastic-plastic fracture mechanics is popularly used for integrity evaluation of major components, however, it is not easy to extract standard specimens from operating facility. This paper examines how ductile fracture toughness is characterized by a small punch testing technique in conjunction with finite element analyses incorporating a damage model. At first, micro-mechanical parameters constituting Rousselier model are calibrated for typical nuclear materials using both estimated and experimental load-displacement (P-$\delta$) curves of miniaturized specimens. Then, fracture resistance (J-R) curves of relatively larger standard CT specimens are predicted by finite element analyses employing the calibrated parameters and compared with corresponding experimental ones. It was proven that estimated results by the proposed method using small punch specimen is promising and might be used as a useful tool for ductile crack growth evaluation.

Realistic Prediction of Post-Cracking Behaviour in Synthetic Fiber Reinforced Concrete Beams (합성섬유보강 콘크리트 보의 균열 후 거동 예측)

  • 오병환;김지철;박대균;원종필
    • Journal of the Korea Concrete Institute
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    • v.14 no.6
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    • pp.900-909
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    • 2002
  • Fibers play a role to increase the tensile strength and cracking resistance of concrete structures. The post cracking behavior must be clarified to predict cracking resistance of fiber reinforced concrete. The purpose of this study is to develop a realistic analysis method for the post cracking behavior of synthetic fiber reinforced concrete members. For this purpose, the cracked section is assumed to behave as a rigid body and the pullout behavior of single fiber is employed. A probabilistic approach is used to calculate effective number of fibers across crack faces. The existing theory is compared with test data and shows good agreement. The proposed theory can be efficiently used to describe the load-deflection behavior, moment-curvature relation, load-crack width relation of synthetic fiber reinforced concrete beams.

Strain-Based Shear Strength Model for Prestressed Beams (프리스트레스트 콘크리트 보를 위한 변형률 기반 전단강도 모델)

  • Kang, Soon-Pil;Choi, Kyoung-Kyu;Park, Hong-Gun
    • Journal of the Korea Concrete Institute
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    • v.21 no.1
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    • pp.75-84
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    • 2009
  • An analytical model for predicting the shear strength of prestressed concrete beams without shear reinforcement was developed, on the basis of the existing strain-based shear strength model. It was assumed that the compression zone of intact concrete in the cross-section primarily resisted the shear forces rather than the tension zone. The shear capacity of concrete was defined based on the material failure criteria of concrete. The shear capacity of the compression zone was evaluated along the inclined failure surface, considering the interaction with the compressive normal stress. Since the distribution of the normal stress varies with the flexural deformation of the beam, the shear capacity was defined as a function of the flexural deformation. The shear strength of a beam was determined at the intersection of the shear capacity curve and the shear demand curve. The result of the comparisons to existing test results showed that the proposed model accurately predicted the shear strength of the test specimens.

Prediction of Failure Behavior for Nuclear Piping Using Curved Wide-Plate Test (흰 광폭평판 시험을 이용한 원자력 배관의 파괴거동예측)

  • Huh, Nam-Su;Kim, Yun-Jae;Choi, Jae-Boong;Kim, Young-Jin;Lim, Hyuk-Soon;Chung, Dae-Yul
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.4
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    • pp.352-361
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    • 2004
  • One important element of the Leak-Before-Break analysis of nuclear piping is how to determine relevant fracture toughness (or the J-resistance curve) for nonlinear fracture mechanics analysis. The practice to use fracture toughness from a standard C(T) specimen is known to often give conservative estimates of toughness. To improve the accuracy, this paper proposes a new method to determine fracture toughness using a nonstandard testing specimen, curved wide-plate in tension. To show validity of the proposed curved wide-plate test, the J-resistance curve from the full-scale pipe test is compared with that from the curved wide-plate test and that from the C(T) specimen. It is shown that the J-resistance curve form the curved wide-plate tension test is similar to, but that from the C(T) specimen is lower than, the J-resistance curve from the full-scale pipe test. Further validation is performed by investigating crack-tip constraint conditions via detailed 3-D FE analyses, which shows that the crack-tip constraint condition in the curved wide-plate tension specimen is indeed similar to that in the full-scale pipe under bending.

Strain-Based Shear Strength Model for Prestressed Concrete Beams (프리스트레스트 콘크리트 보를 위한 변형률 기반 전단강도 모델)

  • Kang, Soon-Pil;Park, Hong-Gun
    • Proceedings of the Korea Concrete Institute Conference
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    • 2008.04a
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    • pp.197-200
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    • 2008
  • An analytical model for predicting the shear strength of prestressed concrete beams was developed, applying the previously proposed strain-based shear strength model. In flexure-compression member without shear reinforcement, compression zone of intact concrete primarily resist to the shear force rather than tension zone. The shear capacity of concrete at the compression zone was defined based on the material failure criteria. The shear capacity of the compression zone was evaluated along the inclined failure surface considering interaction with the normal stress. Since the distribution of normal stress varies due to the flexural deformation of member, the shear capacity was defined as a function of the flexural deformation. Finally, the shear strength was determined at the intersection of the shear capacity curve and the shear demand curve. As a result of the comparisons to prior test data, the proposed model accurately predicted the shear strength of specimens.

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