• Title/Summary/Keyword: bending of curved pipe

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Stress Analysis of Curved Portions of Pipe Loops Used in Ships and Offshore Structures (선박 해양구조물 파이프 루프 곡선부의 응력 해석)

  • Park, Chi-Mo;Bae, Byoung-Il
    • Journal of Ocean Engineering and Technology
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    • v.25 no.5
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    • pp.52-57
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    • 2011
  • Most ships and offshore structures are equipped with a variety of pipes, which inevitably contain curved portions. While it has been a usual practice to conduct bending stress analyses of these curved pipes using the straight-beam theory, this paper adopts two different types of finite elements, straight-beam elements and two-dimensional shell elements, for finite element analyses of a variety of curved pipes. It then compares the analysis results for two different types of elements to determine correction factors, which can be used to transform the bending displacements and bending stresses obtained by straight-beam elements to those obtainable by two-dimensional shell elements. The paper ends with a practical suggestion on how to efficiently use these correction factors to estimate the combined axial and normal stresses in a curved portion of a pipe.

Practical estimation of the plastic collapse limit of curved pipes subjected to complex loading

  • Yan, A.M.;Nguyen, D.H.;Gilles, Ph.
    • Structural Engineering and Mechanics
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    • v.8 no.4
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    • pp.421-438
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    • 1999
  • In this paper a practical limit load estimating procedure is proposed for general pipe-elbow structures subjected to complex loading (in-plane and out-of-plane bending, internal pressure and axial force). The explicit calculating formulae are presented on the basis of theoretical analysis combined with numerical simulation. Von Mises' yield criterion is adopted in both analytical and numerical calculation. The finite element examination shows that the method provides a simple but satisfactory prediction of pipe structures in engineering plastic analysis.

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.

A Study on the Structural Analysis of Curved Portions of Pipe Loops Used in Ships (선박용 파이프 루프 곡선부의 구조해석에 관한 연구)

  • Park, Chi-Mo;Bae, Byoung-Il
    • Journal of Ocean Engineering and Technology
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    • v.24 no.5
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    • pp.88-93
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    • 2010
  • Many pipes that are arranged longitudinally in ships have loops at intervals to prevent the failure of the pipes as they absorb large portions of the axial load caused by the bending of the hull girder and/or thermal loads when the pipes are carrying very hot fluids. Since the loops are curved at corners, an efficient method for conducting the structural analyses of these curved portions is required. In this paper, a pipe loop was analyzed by an analytical method and by the finite-element method in four different ways, i.e., based on straight-beam elements, curved-beam elements, 2-D shell elements, and 3-D solid elements. The results of the five analyses were compared to check the validity of the current curved-beam theory. The paper includes some suggestions on how to analyze the pipe loops efficiently.

Development of Design Formulas for Pipe Loops Used in Ships Considering the Structural Characteristics of Curved Portions (곡선부의 구조 특성을 고려한 선박용 파이프 루프 설계식 개발)

  • Park, Chi-Mo;Bae, Byoung-Il
    • Journal of Ocean Engineering and Technology
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    • v.26 no.5
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    • pp.87-93
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    • 2012
  • Many longitudinally-arranged pipes in ships are equipped with loops as a measure to reduce stresses caused by displacement loads conveyed from the hull girder bending and/or thermal loads of carried fluid of non-ambient temperature. But as the loops have some negative effects such as causing extra manufacturing cost and occupying extra space, the number and the dimensions of the loops need to be minimized. In the meanwhile, a design formula for pipe loops has been developed by modeling them as a spring element of which stresses and axial stiffness are calculated based on the beam theory. But as the beam theory turns out to be inappropriate to deal with the complex structural behavior in the curved corner portion of the loop, this paper aims at improving the previously developed design formula by adopting correction factors which can allow for the gap between the results of beam theory and a more accurate analysis. This paper adopts a finite element analysis with two-dimensional shell elements with some validation work for it. The paper ends with a sample application of the proposed formulas showing their accuracy and efficiency.

Validation of applicability of induction bending process to P91 piping of prototype Gen-IV sodium-cooled fast reactor (PGSFR)

  • Tae-Won Na;Nak-Hyun Kim;Chang-Gyu Park;Jong-Bum Kim;Il-Kwon Oh
    • Nuclear Engineering and Technology
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    • v.55 no.10
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    • pp.3571-3580
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    • 2023
  • The application of the induction bending process to pipe systems in various industrial fields is increasing. Recently, efforts have also been made to apply this bending process to nuclear power plants because it can innovatively reduce welded parts of the curved pipes, such as elbows. However, there have been no cases of the application of induction bending to the piping of nuclear power plants. In this study, the applicability of the P91 induction bending piping for the sodium-cooled fast reactor PGSFR was validated through high temperature low cycle fatigue tests and creep tests using P91 induction bending pipe specimens. The tests confirmed that the materials sufficiently satisfied the fatigue life and the creep rupture life requirements for P91 steel at 550 ℃ in the ASME B&PV Code, Sec. III, Div. 5. The results show that the effects of heating and bending by the induction bending process on the material properties were not significant and the induction bending process could be applicable to piping system of PGSFR well.

Study on Structural Behavior of Pipe Loops Using CAESAR-II (CAESAR-II를 이용한 파이프 루프의 구조 거동 특성 연구)

  • Park, Chi-Mo;Yoon, Seong-Ryong
    • Journal of Ocean Engineering and Technology
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    • v.27 no.2
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    • pp.13-18
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    • 2013
  • Most ships and offshore structures are equipped with a variety of pipes, which inevitably contain curved portions. The structural design of these pipes mostly relies on the commercial code, CAESAR-II, which was especially developed for the structural analysis of pipes. This study conducted stress analyses of the same pipe unit, including loops, using both CAESAR-II and MSC/NASTRAN, and compared the results to investigate the characteristics of CAESAR-II. A parametric study was then conducted of the various design variables of pipe loops using CAESAR-II to draw some useful information about the structural characteristics of the loops.

Behavior of Curved Pipes under In-Plane Bending (면내굽힘에서 곡선배관의 거동특성)

  • Lee, Sang-Ho;Song, Hyeon-Seob
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.9 no.2
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    • pp.480-486
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    • 2008
  • The pipe elbows subjected to in-plane bending moments are analyzed with the finite element method. The results from the finite element analysis are compared with ASME code equations that are theoretical closed form solutions. The geometric nonlinear effects due to the ovalization are explained with the magnitude and the types of the stresses and the flexibilities of the elbows with the emphasis on the bend angles and elbow factors.

Development of Stress Intensity Factor Equation for the Notched Ring Test (NRT) Specimen (Notched Ring Test 저속균열 시험편의 응력확대계수정식화)

  • Pyo, Sooho;Choi, Sunwoong
    • Korean Journal of Materials Research
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    • v.24 no.2
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    • pp.87-92
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    • 2014
  • The Notched Ring Test(NRT) has proven to be very useful in determining the slow crack growth behavior of polyethylene pressure pipes. In particular, the test is simple and an order of magnitude shorter in experimental times as compared to the currently used Notched Pipe Test(NPT), which makes this method attractive for use as the accelerated slow crack growth test. In addition, since the NRT specimen is taken directly from the pipe, having maintained the cross-section, processing induced artifacts that would affect the slow crack growth behavior are not altered. This makes the direct comparison to the slow crack growth specimen in pipe from more meaningful. In this study, for comparison with other available slow crack growth methods, including the NPT, the stress intensity factor equation for NRT specimen was developed and demonstrated of its accuracy within 3% of that obtained from the finite element analysis. The equation was derived using a flexure formula of curved beam bending along with numerically determined geometric factors. The accuracy of the equation was successfully tested on 63, 110, 140, 160, 250, and 400 mm nominal pipe diameters, with crack depth ranging from 15 % to 45 % of the pipe wall thickness, and for standard dimensional ratio(SDR) of 9, 11, and 13.6. Using this equation the slow crack results from 110SDR11 NRT specimen were compared to that from the NPT specimen, which demonstrated that the NRT specimen was equivalent to the NPT specimen in creating the slow crack, however in much shorter experimental times.