• Title/Summary/Keyword: Flaw Analysis

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Probabilistic Evaluation of RV Integrity Under Pressurized Thermal Shock (가압열충격을 받는 원자로용기의 확률론적 건전성 평가)

  • Kim, Jong-min;Bae, Jae-hyun;Sohn, Gap-heon;Yoon, Ki-seok;Choi, Taek-Sang
    • Proceedings of the KSME Conference
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    • 2004.11a
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    • pp.90-95
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    • 2004
  • The probabilistic fracture analysis is used to determine the effects of uncertainties involved in material properties, location and size of flaws, etc, which can not be addressed using a deterministic approach. In this paper the probabilistic fracture analysis is applied for evaluating the RV(Reactor Vessel) under PTS(Pressurised Thermal Shock). A semi-elliptical axial crack is assumed in the inside surface of RV. The selected random parameters are initial crack depth, neutron fluence, chemical composition of material (copper, nickel and phosphorous) and $RT_{NDT}$. The deterministically calculated $K_I$ and crack tip temperature are used for the probabilistic calculation. Using Monte Carlo simulation, the crack initiation probability for fixed flaw and PNNL(Pacific Northwest National Laboratory) flaw distribution is calculated. As the results show initiation probability of fixed flaw is much higher than that of PNNL distribution, the postulated crack sizes of 1/10t in this paper and 1/4t of ASME are evaluated to be very conservative.

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The Comparison of Acceptance Criteria and Flaw Size Measurement between ASME and RCC-M Code in Ultrasonic Examination (초음파검사시 ASME와 RCC-M CODE에 따른 결함 크기측정 및 허용기준 비교평가)

  • Kim, B.C.;Lim, H.T.;Lee, J.P.;Joo, Y.S.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.8 no.1
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    • pp.6-11
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    • 1988
  • The comparison and analysis of flaw detectability, flaw sizing methods and allowable criteria in accordance with the applicable codes, ASME and RCC-M Code, in ultrasonic examination of pressure vessel in nuclear power plants were studied. Accordding to the codes, calibration blocks were made. The artificial flaws such as disc and band types in test specimens were machined. They were detected and evaluated with etch code requirements and measured values were compared with the actual flaws.

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Propose of New Ultrasonic Nondestructive Code Considering Discontinuity Position (불연속부의 위치를 고려한 초음파 비파괴 검사 규격의 개선안)

  • Jeong, Hwa-Young;Shin, Byoung-Chul;Jung, Beom-Seok;Lee, Chang-Moo
    • Journal of the Korea institute for structural maintenance and inspection
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    • v.3 no.4
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    • pp.173-178
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    • 1999
  • KS-code(KS B 0896) for nondestructive ultrasonic testing classifies the quality level by ratio of flaw size to plate thickness only. But stress distributions using verification(3 point bending test) show that location of the flaws is more important than the flaw size. So. KS-code should take the effect of flaw location for classifying the quality level of welded steel structures.

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Stress Corrosion Crack Growth Evaluation in Primary Loop of Nuclear Power Plant (원전 주배관의 응력부식 가상결함 성장에 대한 잔류응력 영향 평가)

  • Yang, J.S.;Park, C.Y.;Yoon, K.S.;Kang, S.Y.;Oho, J.K.
    • Proceedings of the KSME Conference
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    • 2004.04a
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    • pp.274-277
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    • 2004
  • The most important mode of subcritical crack growth is primary water stress corrosion crack, which was the reported mechanism from the root cause analysis of the crack in the bimetallic welds. Stress corrosion crack growth evaluations was carried out for several flaw shapes of both axial and circumferential flaws, using the steady-state stresses including residual stresses. This evaluation considered the possibility of additional flaws in the primary loops of nuclear power plant, even though no such flaws have been identified by Ultrasonic Test. Consequently, Results show that the predicted flaw sizes will determine acceptability for continued service and maintenance.

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Development of Diagnosis Technique for Converter Bearings by Using Acoustic Emission (음향방출기법을 이용한 전로베어링 안전진단 기술개발)

  • 박경조
    • Journal of the Korean Society of Safety
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    • v.18 no.2
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    • pp.6-15
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    • 2003
  • A method is presented for diagnosing the converter bearings by using acoustic emission. The flaking mechanism causing the large-scale bearing for furnace to flaw is investigated and a possibility of defect is verified by Finite Element method. he diagnosis logic is proposed fir detecting the flaw of a non-continuous rotating machine. It is proved that the acoustic emission energy can be used as a representative parameter for an acoustic event. Applying the method to the tilting bearings for steel mill in operation, the effectiveness of this logic is evaluated. It is shown that AE signal is generated only when the bearing is tilting, and the trend analysis can be focused upon this process.

Complement of Ultrasonic Nondestructive Testing Code using Finite Element Method (유한요소법을 이용한 초음파 비파괴검사 규격의 보완)

  • Jeong, Hwa-Young;You, Seung-Youp;Shin, Byoung-Churl;Jung, Beom-Seok;Yi, Chang-Moo
    • Journal of the Korea institute for structural maintenance and inspection
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    • v.3 no.1
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    • pp.157-162
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    • 1999
  • KS-code(KS B 0896) for nondestructive ultrasonic testing judge the quality level by ratio of flaw size to plate thickness only. But stress distributions using finite element analysis show that location of the flaws are more important than the flaw size. So, KS-code should take into account of flaw location for judging the quality level of welded steel structures.

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The Effect of Analysis Variables on the Failure Probability of the Reactor Pressure Vessel by Pressurized Thermal Shock (가압열충격에 의한 원자로 압력용기의 파손확률에 미치는 해석변수의 영향)

  • Jang, Chang-Heui;Jhung, Myung-Jo;Kang, Suk-Chull;Choi, Young-Hwan
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.6
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    • pp.693-700
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    • 2004
  • The probabilistic fracture mechanics(PFM) is a useful analytical tool to assess the integrity of reactor pressure vessel(RPV) at the event of pressurized thermal shock(PTS). In PFM, the probabilities of flaw initiation and propagation are estimated by comparing the applied stress intensity factor with the fracture toughness calculated by the simulation of various stochastic variables. It is known that the results of PFM analyses are dependent on the choice of the stochastic parameters and assumptions. Of the various variables and assumptions, we investigated the effects of the RT$_{NDT}$ shift equations, fracture toughness curves, and flaw distributions on the PFM results for the three PTS transients. The results showed that the combined effects of the RT$_{NDT}$ shift equations and fracture toughness curves are complicated and dependent on the characteristics of the transients, the chemistry of the materials, the fast neutron fluence, and so on.

A Study on the Performance of the Ring-type Impulse Turbine for Wave Energy Conversion (파력발전용 링타입 임펄스터어빈의 성능 해석)

  • HYUN BEOM-SOO;MOON JAE-SEUNG;HONG SEOK-WON;KIM KI-SUP
    • Journal of Ocean Engineering and Technology
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    • v.20 no.1 s.68
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    • pp.20-25
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    • 2006
  • This paper deals with the design and aerodynamic analysis of a so-called 'ring-type' impulse turbine for wave energy conversion. Numerical analysis was performed using the CFD cock, FLUENT. The main idea of the proposed turbine rotor was to minimize the adverse effect of tip clearance of the turbine blade; the design was borrowed from a ducted propeller with connected ring tip for special purpose marine vehicles. Results show that the efficiency increases up to $10\%$, depending on flaw coefficient, with the higher flaw coefficient yielding better efficiency. Decrease of input coefficient CA was the main reason for higher efficiency. Performance of ring-type rotor at various design parameters, as well as flaw conditions, was investigated, and the advantages and the disadvantages of the present impulse turbine were also discussed.

Construction of the P-T Limit Curve for the Nuclear Reactor Pressure Vessel Using Influence Coefficient Methods : Cooldown Curve (영향계수를 이용한 원자로 압력용기의 운전제한곡선 작성 : 냉각곡선)

  • Jang, Chang-Hui
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.26 no.3
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    • pp.505-513
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    • 2002
  • During heatup and cooldown of pressurized water reactor, thermal stress was generated in the reactor pressure vessel (RPV) because of the temperature gradient. To prevent potential failure of RPV, pressure was required to be maintained below the P-T limit curves. In this paper, several methods for constructing the P-T limit curves including the ASME Sec. XI, App. G method were explained and the results were compared. Then, the effects of the various parameters such as flaw size, flaw orientation, cooldown rate, existence of chad, and reference fracture toughness, were evaluated. It was found that the current ASME Sec. XI App. G method resulted in the most conservative P-T limit curve. As the more accurate fracture mechanics analysis results were used, some of the conservatism can be removed. Among the parameters analysed, reference flaw orientation and reference fracture toughness curve had the greatest effect on the resulting P-T limit curves.

Fatigue life prediction of multiple site damage based on probabilistic equivalent initial flaw model

  • Kim, JungHoon;Zi, Goangseup;Van, Son-Nguyen;Jeong, MinChul;Kong, JungSik;Kim, Minsung
    • Structural Engineering and Mechanics
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    • v.38 no.4
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    • pp.443-457
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    • 2011
  • The loss of strength in a structure as a result of cyclic loads over a period of life time is an important phenomenon for the life-cycle analysis. Service loads are accentuated at the areas of stress concentration, mainly at the connection of components. Structural components unavoidably are affected by defects such as surface scratches, surface roughness and weld defects of random sizes, which usually occur during the manufacturing and handling process. These defects are shown to have an important effect on the fatigue life of the structural components by promoting crack initiation sites. The value of equivalent initial flaw size (EIFS) is calculated by using the back extrapolation technique and the Paris law of fatigue crack growth from results of fatigue tests. We try to analyze the effect of EIFS distribution in a multiple site damage (MSD) specimen by using the extended finite element method (XFEM). For the analysis, fatigue tests were conducted on the centrally-cracked specimens and MSD specimens.