• Title/Summary/Keyword: ASME Code

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Evaluation of Local Allowable Wall Thickness of Thinned Pipe Subjected to Internal Pressure and Bending Moment (내압과 굽힘하중하에서 감육배관의 국부허용두께 평가)

  • Kim, Jin-Won;Park, Chi-Yong;Kim, Beom-Nyeon
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.25 no.1
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    • pp.81-88
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    • 2001
  • This study proposed an analytical method to evaluate a local allowable wall thickness (LAWT) for locally thinned pipe subjected to internal pressure and bending moment. In this method, the stresses in the thinned region were calculated by finite element analysis and plastic collapse was applied as a failure criterion of thinned pipe. Using this method, LAWT for a simplified thinned pipe was evaluated with variation in axial extent of thinned area, and it was compared with allowable wall thickness provided by previous pipe wall thickness criteria. The results showed that the LAWT was lower, about 50%, than that calculated by construction code or ASME Code N-597, and it was higher, about 2 times, than that estimated by evaluation model based on pipe experiments. In addition, LAWT was decreased with increasing axial extent of thinned area and saturated with further increase in axial extent. And, the variation in LAWT with axial extent of thinned area depended on type of load, especially a magnitude of bending moment, considering in the evaluation.

A Study on Design Criteria of Piping System in Petrochemical Plant (석유화학 플랜트의 배관계 설계기준에 대한 연구)

  • Min, Sun-Kuo;Choi, Myung-Jin
    • Journal of the Korean Society for Precision Engineering
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    • v.19 no.6
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    • pp.192-199
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    • 2002
  • Largely, there are three kinds of the design criteria of piping system in petrochemical plant. The first is on the pipe thickness in accordance with the design pressure of piping system. The second is on the static state evaluation by thermal growth and the other is on the dynamic evaluation by piping vibration. According to the ASME B31.3 code, the internal pressure design thickness fur straight pipe shall be calculated as a code formula. And the static design by thermal displacement is defined 7000 cycles of fatigue life in operating the piping system with a design condition. However, the dynamic design evaluation in comparative with small displacements of high frequencies to the static condition has not established clearly the method, yet. So, this study purposes to present the trial of a proposal of dynamic design criterion on the basis of static design method.

Prediction of Creep Stress in High Temperature Piping System Using Elastic Follow-up Factor (탄성추종계수를 이용한 고온 배관계의 크리프 응력 예측)

  • Seo, Jun-Min;Youn, Gyo-Geun;Lee, Hyun-Jae;Oh, Young-Jin;Kim, Yun-Jae
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.14 no.1
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    • pp.32-37
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    • 2018
  • When designing high temperature piping system, creep phenomena must be considered. Since ASME code does not provide detailed methods of design by rule (DBR) for high temperature piping, Finite element analysis should be performed. However, In the case of piping system with frequent design changes, creep analysis of the entire piping system for every change is ineffective and practically impossible. Therefore, based on elastic and elastic-plastic analysis, which takes a relatively short time, the creep stress is predicted by using elastic follow-up factor method provided in R5 code and plastic-creep analogy presented by Hoff. The predicted creep stress for a virtual piping system was compared with the creep analysis result and the two results showed similar stress relaxation tendency in time.

High-Temperature Tensile Strengths of Alloy 617 Diffusion Weldment (Alloy 617 확산용접재의 고온 인장강도)

  • Sah, Injin;Hwang, Jong-Bae;Kim, Eung-Seon
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.14 no.1
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    • pp.15-23
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    • 2018
  • A compact heat exchanger is one of critical components in a very high temperature gas-cooled reactor (VHTR). Alloy 617 (Ni-Cr-Co-Mo) is considered as one of leading candidates for this application due to its excellent thermal stability and strengths in anticipated operating conditions. On the basis of current ASME code requirements, sixty sheets of this alloy are prepared for diffusion welding, which is the key technology to have a reliable compact heat exchanger. Optical microscopic analysis show that there are no cracks, incomplete bond, and porosity at/near the interface of diffusion weldment, but Cr-rich carbides and Al-rich oxides are identified through high resolution electron microscopic analysis. In high-temperature tensile testing, superior yield strengths of the diffusion weldment compared to the code requirement are obtained up to 1223 K ($950^{\circ}C$). However, both tensile strength and ductility drop rapidly at higher temperature due to the insufficient grain boundary migration across the interface of diffusion weldment. Best fit curves for minimum yield strength and average tensile strength are drawn from the experimental tensile results of this study.

Safety Evaluation Based on Structural Analysis of Cylinder Valves for Fuel Cell Vehicles (구조해석을 이용한 수소 연료전지 자동차 압력용기 밸브의 안전성 평가)

  • Lee, Hyo Ryeol;Ahn, Jung Hwan;Shin, Jin Oh;Kim, Hwa Young
    • Journal of the Korean Society of Manufacturing Technology Engineers
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    • v.25 no.3
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    • pp.189-197
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    • 2016
  • Green vehicles include electric vehicles, natural gas vehicles, and fuel cell vehicles (FCVs). In FCVs, pressure vessels have cylinder valves to control hydrogen flow. These valves should be of high quality in terms of safety because hydrogen is stored at ultra-high pressure in pressure vessels. Hence, safety evaluation of these valves is necessary to secure the safety of the FCV. A structural analysis of the cylinder valve was conducted in this study by using a commercial finite element analysis code. The results showed that the safety factor of valve component ranged 1.06-186.44. After categorizing, the stress components at critical points of the cylinder valve parts were evaluated using the corresponding allowable design criteria in the ASME code. The pressurization cycle test was performed as per the regulation to evaluate the safety of the valve.

Investigation on the thermal butt fusion performance of the buried high density polyethylene piping in nuclear power plant

  • Kim, Jong-Sung;Oh, Young-Jin;Choi, Sun-Woong;Jang, Changheui
    • Nuclear Engineering and Technology
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    • v.51 no.4
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    • pp.1142-1153
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    • 2019
  • This paper presents the effect of fusion procedure on the fusion performance of the thermal butt fusion in the safety class III buried HDPE piping per various tests performed, including high speed tensile impact, free bend, blunt notched tensile, notched creep, and PENT tests. The suitability of fusion joints and qualification procedures was evaluated by comparing test results from the base material and buttfusion joints. From the notched tensile test result, it was found that the fused joints have much lower toughness than the base material. It was also identified that the notched tensile test is more desirable than the high speed tensile impact and free bend tests presented in the ASME Code Case N-755-3 as a fusion qualification test method. In addition, with regard to the single low-pressure fusion joint performances, the procedure given by the ISO 21307 was determined to be better that the one specified in the Code Case N-755-3.

Effect of Wall Thinned Shape and Pressure on Failure of Wall Thinned Nuclear Piping Under Combined Pressure and Bending Moment (감육형상 및 내압이 원자력 감육배관의 파단에 미치는 영향 -내압과 굽힘모멘트가 동시에 작용하는 경우-)

  • Shim, Do-Jun;Lim, Hwan;Choi, Jae-Boong;Kim, Young-Jin;Kim, Jin-Won;Park, Chi-Yong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.27 no.5
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    • pp.742-749
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    • 2003
  • Failure of a pipeline due to local wall thinning is getting more attention in the nuclear power plant industry. Although guidelines such as ANSI/ASME B31G and ASME Code Case N597 are still useful fer assessing the integrity of a wall thinned pipeline, there are some limitations in these guidelines. For instance, these guidelines consider only pressure loading and thus neglect bending loading. However, most Pipelines in nuclear power plants are subjected to internal pressure and bending moment due to dead-weight loads and seismic loads. Therefore, an assessment procedure for locally wall thinned pipeline subjected to combined loading is needed. In this paper, three-dimensional finite element(FE) analyses were performed to simulate full-scale pipe tests conducted for various shapes of wall thinned area under internal pressure and bending moment. Maximum moments based on true ultimate stress(${\alpha}$$\sub$u,t/) were obtained from FE results to predict the failure of the pipe. These results were compared with test results, which showed good agreement. Additional finite element analyses were performed to investigate the effect of key parameters, such as wall thinned depth, wall thinned angle and wall thinned length, on maximum moment. Also, the effect of internal pressure on maximum moment was investigated. Change of internal pressure did not show significant effect on the maximum moment.

An Experimental Study on Failure Behavior of TP316 Stainless Steel Pipe with Local Wall Thinning and Cracking (국부 감육과 균열이 발생한 TP316 스테인리스강 배관의 파괴거동에 관한 실험적 연구)

  • Cheung, Jin Hwan;Kim, In Tae;Choi, Seock Jin;Choi, Hyung Suk;Kim, Hee Sung
    • Journal of Korean Society of Steel Construction
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    • v.24 no.6
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    • pp.647-657
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    • 2012
  • Although nuclear power plant piping system is designed conforming to design specifications, the piping systems are deteriorated with increase in service life. In this study, monotonic and cyclic loading tests were carried out on TP316 stainless steel pipe specimens, and the effect of local wall thinning and cracking on failure behavior was investigated. In the tests, 0%, 35% and 75% wall thinning and cracking of initial thickness were artificially introduced to inside elbow and straight pipe specimens, and internal pressures of 20MPa were applied to simulate real operation condition. From the test results, the effect of local wall thinning and cracking on failure mode, ultimate load, number of cycle and strain energy was presented, and maximum bending moment was compared with allowable bending moment calculated by ASME code.

Seismic Design and Analysis of Seismically Isolated KALIMER Reactor Structures (면진된 KALIMER 원자로 구조물의 내진설계 및 지진해석)

  • 이형연
    • Journal of the Earthquake Engineering Society of Korea
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    • v.3 no.1
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    • pp.75-92
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    • 1999
  • In this paper, the seismic analysis model for seismically isolated KALIMER reactor structures is developed and the modal analysis and the seismic time history analysis are carried out for seismic isolation and non-isolation cases. To check the seismic stress limit according to the ASME Code, the equivalent seismic stress analyses are preformed using the 3-D finite element model. From the seismic stress analysis, the seismic margins are calculated for structural members. The limit of seismic load is defined to show that the maximum input acceleration ensures the structural safety for seismic load. In comparison of seismic responses between seismic isolation and non-isolation cases, the seismic isolation design gives significantly reduced acceleration responses and relative displacements between structures. The seismic margin of KALIMER reactor structure is high enough to produce the limit seismic load 0.8g.

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A Study on the Ultrasonic Inspection Method in High Attenuation Welds using Minimization-Polarity Threshold Algorithm (최소극 문턱치 알고리즘을 이용한 고감쇠 용접부에서 초음파 검사방법에 관한 연구)

  • Koo, Kil-Mo;Park, Chi-Seung;Choi, Jong-Ho;Ko, Duck-Young
    • Journal of the Institute of Electronics Engineers of Korea TE
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    • v.37 no.3
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    • pp.30-36
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    • 2000
  • In this paper, an ultrasonic testing method for inspection of high attenuation welding area using the minimum Polarity threshold algorithm which combines the minimum amplitude selection algorithm and polarity threshold algorithm is suggested to increase the signal to noise ratio of the flow signal. In order to confirm the usefulness of the suggested algorithm, experiments were performed using four probes and standard specimens following the ASME Xl Code. As a result, scattering signals were observed from the SE(safe end) and CCSS (centrifugal casting stainless steel) materials due to the microstructural characteristical, and the detectability was reduced due to the highly attenuated signal from the weldment area, but it was conformed that using the suggested algorithm, the signal to noise ratio increased about 2.6.

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