• Title/Summary/Keyword: Cracked Piping

Search Result 32, Processing Time 0.028 seconds

An Experimental Study on the Fracture Behavior of Nuclear Piping System with a Circumferential Crack(I) - Estimation of Crack Behavior in Straight Piping - (원주방향균열이 존재하는 원전 배관계통의 파괴거동에 관한 실험적 연구(I) - 직관부에서의 균열거동 평가 -)

  • Choi, Young-Hwan;Park, Youn-Won;Wilkowski, Gery
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.23 no.7 s.166
    • /
    • pp.1182-1195
    • /
    • 1999
  • The purpose of this study is to investigate experimentally the effects of both seismic loading and crack length on the fracture behavior of piping system with a circumferential crack in nuclear power plants. The experiments were performed using both large scale piping system facility and 4 points bending test machine under PWR operating conditions. The difference in the load carrying capacities between cracked piping and non-cracked piping was also investigated using the results from experiments and numerical calculations. The results obtained from the experiments and estimation are as follows : (1) The safety margin under seismic loading is larger than those under quasi static loading or simple cyclic loading. (2) There was no significant effect of crack length on tincture behavior of piping system with both a surface crack and a through-wall crack. (3) The load carrying capacity in cracked piping was reduced by factors of 7 to 46 compared to non-cracked piping.

Review of Acceleration Methods for Seismic Analysis of Through-Wall Cracked Piping from the Viewpoint of Linear Elastic Fracture Mechanics (지진 해석시 선형탄성파괴역학 측면에서의 관통 균열 배관에 대한 가진 방법론 검토)

  • Kim, Jong Sung;Kim, Yong Woo
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.38 no.10
    • /
    • pp.1157-1162
    • /
    • 2014
  • Two acceleration methods, an effective force method (or inertia method) and a large mass method, have been applied for performing time history seismic analysis. The acceleration methods for uncracked structures have been verified via previous studies. However, no study has identified the validity of these acceleration methods for cracked piping. In this study, the validity of the acceleration methods for through-wall cracked piping is assessed via time history implicit dynamic elastic seismic analysis from the viewpoint of linear elastic fracture mechanics. As a result, it is identified that both acceleration methods show the same results for cracked piping if a large mass magnitude and maximum time increment are adequately selected.

Development of a Piping Integrity Evaluation Simulator Based on the Hardware-in-the-Loop Simulation (하드웨어-인-더-루프 기반의 배관 평가 시뮬레이터의 개발)

  • Kim, Yeong-Jin;Heo, Nam-Su;Cha, Heon-Ju;Choe, Jae-Bung;Pyo, Chang-Ryul
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.25 no.7
    • /
    • pp.1031-1038
    • /
    • 2001
  • In order to verify the analytical methods predicting failure behavior of cracked piping, full-scale pipe tests are crucial in nuclear power plant piping. For this reason, series of international test programs have been conducted. However, full-scale pipe tests require expensive testing equipment and long period of testing time. The objective of this paper is to develop a test system which can economically simulate the full-scale pipe test regarding the integrity evaluation. This system provides the failure behavior of cracked pipe by testing a wide-plate specimen. The system provides the failure behavior of cracked pipe by testing a wide-plate specimen. The system was developed for the integrity evaluation of nuclear piping based on the methodology of hardware-in-the-loop (HiL) simulation. Using this simulator, the piping integrity can be evaluated based on the elastic-plastic behavior of full-scale pipe, and the high cost full-scale pipe test may be replaced with this economical system.

Applicability of Existing Fracture Initiation Models to Modern Line Pipe Steels

  • Shim, Do Jun
    • Transactions of the Korean Society of Pressure Vessels and Piping
    • /
    • v.12 no.2
    • /
    • pp.1-24
    • /
    • 2016
  • The original fracture criteria developed by Maxey/Kiefner for axial through-wall and surface-cracked pipes have worked well for many industries for a large variety of relatively low strength and toughness materials. However, newer line pipe steels have some unusual characteristics that differ from these older materials. One example is a test data that has demonstrated that X80 line-pipe with an axial through-wall-crack can fail at pressures about 30 percent lower than predicted with commonly used analysis methods for older steels. Thus, it is essential to review the currently available models and investigate the applicability of these models to newer high-strength line pipe materials. In this paper, the available models for predicting the failure behavior of axial-cracked pipes (through-wall-cracked and external surface-cracked pipes) were reviewed. Furthermore, the applicability of these models to high-strength steel pipes was investigated by analyzing limited full-scale pipe fracture initiation test results. Based on the analyzed results, the shortcomings of the available models were identified. For both through-wall and surface cracks, the major shortcomings were related to the characterization of the material toughness, which generally leads to non-conservative predictions in the J-T analyses. The findings in this paper may be limited to the test data that were consider for this study. The requisite characteristics of a potential model were also identified in the present paper.

Determination of Chaboche Cyclic Combined Hardening Model for Cracked Component Analysis Using Tensile and Cyclic C(T) Test Data (표준 인장시험과 반복하중 C(T) 시험을 이용한 균열해석에서의 Chaboche 복합경화 모델 결정법)

  • Hwang, Jin Ha;Kim, Hune Tae;Ryu, Ho Wan;Kim, Yun Jae;Kim, Jin Weon;Kweon, Hyeong Do
    • Transactions of the Korean Society of Pressure Vessels and Piping
    • /
    • v.15 no.2
    • /
    • pp.31-39
    • /
    • 2019
  • Cracked component analysis is needed for structural integrity analysis under seismic loading. Under large amplitude cyclic loading conditions, the change in material properties can be complex, depending on the magnitude of plastic strain. Therefore the cracked component analysis under cyclic loading should consider appropriate cyclic hardening model. This study introduces a procedure for determining an appropriate cyclic hardening model for cracked component analysis. The test material was nuclear-grade TP316 stainless steel. The material cyclic hardening was simulated using the Chaboche combined hardening model. The kinematic hardening model was determined from standard tensile test to cover the high and wide strain range. The isotropic hardening model was determined by simulating C(T) test under cyclic loading using ABAQUS debonding analysis. The suitability of the material hardening model was verified by comparing load-displacement curves of cyclic C(T) tests under different load ratios.

Plastic Limit Pressure Solutions for Cracked Pipes Using 3-D Finite Element Method (3차원 유한요소해석을 통해 도출한 균열배관의 소성한계압력식)

  • Shim, Do-Jun;Huh, Nam-Su;Kim, Yun-Jae;Kim, Young-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.27 no.1
    • /
    • pp.26-33
    • /
    • 2003
  • Based on detailed FE limit analyses, the present paper provides tractable approximations fer plastic limit pressure solutions fur axially through-wall-cracked pipe; axially (inner) surface-cracked pipe; circumferentially through-wall-cracked pipe; and circumferentially (inner) surface-cracked pipe. In particular, for surface crack problems, the effect of the crack shape, the semi-elliptical shape or the rectangular shape, on the limit pressure is quantified. Comparisons with existing analytical and empirical solutions show a large discrepancy in circumferential short through-wall cracks and in surface cracks (both axial and circumferential). Being based on detailed 3-D FE limit analysis, the present solutions are believed to be the most accurate, and thus to be valuable information not only for plastic collapse analysis of pressurised piping but also for estimating non-linear fracture mechanics parameters based on the reference stress approach.

Application of cohesive zone model to large scale circumferential through-wall and 360° surface cracked pipes under static and dynamic loadings

  • Moon, Ji-Hee;Jang, Youn-Young;Huh, Nam-Su;Shim, Do-Jun;Park, Kyoungsoo
    • Nuclear Engineering and Technology
    • /
    • v.53 no.3
    • /
    • pp.974-987
    • /
    • 2021
  • This paper presents ductile fracture simulation of full-scale cracked pipe for nuclear piping materials using the cohesive zone model (CZM). The main objective of this study is to investigate the applicability of CZM to predict ductile fracture of cracked pipes with various crack shapes and under quasi-static/dynamic loadings. The transferability of the traction-separation (T-S) curve from a small-scale specimen to a full-scale pipe is demonstrated by simulating small- and full-scale tests. T-S curves are calibrated by comparing experimental data of compact tension specimens with finite element analysis results. The calibrated T-S curves are utilized to predict the fracture behavior of cracked pipes. Three types of full-scale pipe tests are considered: pipe with circumferential through-wall crack under quasistatic/dynamic loadings, and with 360° internal surface crack under quasi-static loading. Computational results using the calibrated T-S curves show a good agreement with experimental data, demonstrating the transferability of the T-S curves from small-scale specimen.

Evaluation of Load-Carrying Capacities for Cracked Pipes (균열이 존재하는 배관의 하중 지지능력 평가)

  • Jang, Yun-Seok;Kim, Hyeon-Su;Jin, Tae-Eun
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.25 no.9
    • /
    • pp.1350-1358
    • /
    • 2001
  • During the last decade, a number of experiments and numerical analyses had been performed in conjunction with the development of simplified analytical methods to estimate the fracture behavior of cracked piping in nuclear power plant. However, the necessity of further investigation for the analytical methods was issued because of the discrepancies with the experimental data. The objective of this paper is to find out the optimum methods to evaluate the load-carrying capacities for cracked pipes. To do this, numerous analytical and finite element analyses were carried out for various pipe and crack geometries and materials. These results were synthesized for crack shapes and can be used as basic data for leak before analyses and risk informed inspections.

Root Cause Analysis and Structural Integrity Evaluation for a Crack in a Reactor Vessel Upper Head Penetration Nozzle (원자로 상부헤드 관통노즐 균열에 대한 원인분석 및 건전성 평가)

  • Lee, Kyoung-Soo;Lee, Sung-Ho;Lee, Jeong-Seog;Lee, Jae-Gon;Lee, Seung-Gun
    • Transactions of the Korean Society of Pressure Vessels and Piping
    • /
    • v.9 no.1
    • /
    • pp.56-61
    • /
    • 2013
  • This paper presents the results of integrity assessment for the cracks happened in reactor vessel upper head penetration nozzles. The crack morphology for a boat sample from crack area was analyzed through microscope. The stress condition including weld residual stress around crack was analyzed using finite element analysis. From the results of crack morphology and stress condition, the crack was concluded as primary water stress corrosion cracking. The integrity of the cracked nozzle was assessed by the methodology provided in ASME Section XI. According to the assessment results, the remaining life of the cracked nozzle was 1.43 yrs. and the plant decided to repair it.

Evaluation of Limit Loads for Circumferentially Cracked Pipes Under Combined Loadings (원주방향 표면 결함이 존재하는 배관에 가해지는 비틀림을 포함한 복합하중에 대한 한계하중식 제시)

  • Ryu, Ho-Wan;Han, Jae-Jun;Kim, Yun-Jae
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.39 no.5
    • /
    • pp.453-460
    • /
    • 2015
  • Since the Fukushima nuclear accident, several researchers are extensively studying the effect of torsion on the piping systems In nuclear power plants. Piping installations in power plants with a circumferential crack can be operated under combined loading conditions such as bending and torsion. ASME Code provides flaw evaluations for fully plastic fractures using limit load criteria for the structural integrity of the cracked pipes. According to the recent version of Code, combined loadings are provided only for the membrane and bending. Even though actual operating conditions have torsion loading, the methodology for evaluating torsion load is not established. This paper provides the results of limit load analyses by using finite element models for circumferentially cracked pipes under pure bending, pure torsion, and combined bending and torsion with tension. Theoretical limit load solutions based on net-section fully plastic criteria are suggested and verified with the results of finite element analyses.