• Title/Summary/Keyword: LBB Test

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Effect of Hydride of the PHWR Pressure Tube on the LBB Evaluation (중수로 압력관의 수화물이 LBB평가에 미치는 영향)

  • Oh, Dong-Joon;Kim, Young-Suk
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.5
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    • pp.610-616
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    • 2004
  • The aim of this study was to investigate the hydride embrittlement when the LBB evaluation was carried out for the integrity of PHWR Pressure Tubes. The transverse tensile and CCT toughness tests were performed at three hydrogen concentrations while the test temperatures were changed (RT to 30$0^{\circ}C$). Both the transverse tensile and the fracture toughness tests showed the hydrogen embitterment clearly at RT but this phenomenon was disappeared while the test temperature arrived at 25$0^{\circ}C$. Using the DHC test results, the CCL and LBB time were calculated and compared. The hydride embrittlement at the LBB evaluation made the LBB time short definedly. If the operating temperature, DHCV and LBB deterministic parameters such as A and m were known, LBB time could be estimated without the calculation of CCL.

반복 하중을 받는 구조용재료의 파단전누설 ( LBB ) 조건에 관한 연구 ( Study on the LBB Conditions of Structure Material under Cyclic Load )

  • Nam, Ki-Woo;Kotoji Ando
    • Journal of the Korean Society of Fisheries and Ocean Technology
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    • v.26 no.4
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    • pp.380-386
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    • 1990
  • The high stress, low cycle fatigue test were carried out on HT80 plates with artificial part-through notch. The LBB conditions by the net section stress approach was examined in detail. Finite element methods for the state of deformation were also applied and the results were compared with the results from experiments. From the test results, it was noted that the LBB condition in fatigue test was dependent upon the maximun load change before and after the crack penetration. The LBB criterion By the net section stress approach were slightly dependent on initial crack size. It was shown that the state of deformation can be used to predict whether the component is likely to show LBB condition or they will be broken rapidly.

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Hydride Embrittlement Behavior at the LBB Evaluation of PHWR Pressure Tube (중수로 압력관 LBB 평가에서의 수소화물에 의한 취화거동)

  • Oh, Dong-Joon;Kim, Young-Suk
    • Proceedings of the KSME Conference
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    • 2003.11a
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    • pp.1192-1197
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    • 2003
  • The aim of this study is to investigate the hydride embrittlement when the LBB evaluation is carried out for the integrity of PHWR Pressure Tubes. The transverse tensile and CCT tests were performed at three hydrogen concentrations while the test temperatures were changed (RT to $300^{\circ}C$). The specimens were directly machined from the pressure tube retaining original curvature. Both the transverse tensile and the fracture toughness tests showed the hydrogen embrittlement clearly at RT but this phenomenon was disappeared while the test temperature arrived over $250^{\circ}C$. Using the DHC test results, the CCL and LBB time were calculated and compared. The hydride embrittlement behavior at the LBB evaluation was definitely showed.

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REVIEW OF DYNAMIC LOADING J-R TEST METHOD FOR LEAK BEFORE BREAK OF NUCLEAR PIPING

  • Oh, Young-Jin;Hwang, Il-Soon
    • Nuclear Engineering and Technology
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    • v.38 no.7
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    • pp.639-656
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    • 2006
  • In order to apply the leak before break (LBB) concept to nuclear piping systems, the dynamic strain aging effect of low carbon steel materials has to be taken into account, in compliance with the requirements of the Korean Standard Review Guide (KSRG) 3.6.3-1. For this goal, J-R tests are needed for a range of various temperatures and loading rates, including dynamic loading conditions. In the dynamic loading J-R test, the unloading compliance method can not be applied to measure the crack growth and direct current potential drop (DCPD) method; this method also has a problem defining the crack initiation point. The normalization method is known as a very useful method to determine the J-R curve under dynamic loading because it does not need additional equipment or complicated loading sequences such as electric current or unloading. This method was accepted by the American Society for Testing and Materials (ASTM) as a standard test method E1820 A15 in 2001. However, it has not yet been clearly verified yet if the normalization method is sufficiently reliable to be applied to LBB. In this study, the basic background of the J-integral, LBB and dynamic loading J-R test are explained, and the current status for dynamic loading J-R test methods are reviewed from the view point of LBB for nuclear piping. In particular, the theoretical and historical background of the normalization method which has received attention recently, is summarized. Recent studies for this method are introduced and future works are suggested that may improve the reliability of LBB for nuclear piping.

Effects of Specimen Size and Side-groove on the Results of J-R Fracture Toughness Test for LBB Evaluation (LBB 평가를 위한 J-R 파괴인성시험 결과에 미치는 시편 형상과 측면 홈의 영향)

  • Kim, Jin Weon;Choi, Myung Rak;Oh, Young Jin;Park, Heung Bae;Kim, Kyung Su
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.7
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    • pp.729-736
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    • 2015
  • In this study, the effects of specimen size and side-groove on the results of the J-R test for leak-before-break (LBB) evaluation were investigated. A series of J-R tests were conducted at both RT and $316^{\circ}C$, using three different sizes of compact tension (CT) specimens machined from SA508 Gr.1a piping material: 12.7 mm-thick 1T-CT, 25.4 mm-thick 1T-CT, and 25.4 mm-thick 2T-CT with and without side-groove. The results showed that side-grooving reduced the J-R curve for all specimens and the effect of side-grooving was more significant at $316^{\circ}C$ than at RT. As the thickness of the specimens decreased and the width of the specimens increased, the J-R curve slightly decreased at RT but it increased at $316^{\circ}C$. However, the variation in the J-R curve of SA508 Gr.1a with the thickness and width of CT specimen was insignificant.

Evaluation of Material Properties for Yonggwang Nuclear Piping System(I)-Shutdown Cooling System- (영광원자력 배관소재의 재료물성치 평가 (1)-정지냉각계통-)

  • 석창성;최용식;장윤석;김종욱
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.18 no.5
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    • pp.1106-1116
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    • 1994
  • Leak Before Break(LBB) design concept is applied to piping systems of newly-built Yonggwang 3, 4 nuclear generating stations as a design alternative to the provision of pipe whip restraints, in recognition of the questionable benefits of providing such restraints. The objective of this paper is to evaluate the material properties (tensile and fracture toughness) of SA312 TP316 stainless steel and their associated welds manufactured for shutdown cooling system of Yonggwang 3, 4 nuclear generating stations. Effect of various parameters such as specimen orientation, test temperature, welding on material properties were examined.

A Model Estimating the Propagation Behavior of through cracks in Aluminum alloy A5083-O for LNG Tank (LNG탱크용 알루미늄합금 A5083-O의 관통균열 전파거동 예측 모델)

  • 김영식;조상명;김종호
    • Journal of Ocean Engineering and Technology
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    • v.12 no.1
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    • pp.50-57
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    • 1998
  • The leak before break(LBB) concept is generalized on the design of LNG tanks, pressure vessels and nuclear reactor in that any leakage of containment, in whatever amount, will not result in catastropic failure. For this purpose it is necessary to determine the surface crack shape, the opening displacement and the risk of catastropic brittle fracture when it becomes a through crack. In this study the crack propagation behavior of surface flaws and the crack opening displacement of through cracks under combined membrane and bending stresses were investigated with fatigue tests and fracture toughness test of aluminium alloy A5083-O. And fracture mechanics analysis of the crack opening displacement of through cracks were made in order to develop a new model expressing the behaviors of COD under combined membrane and bending stresses.

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Development of Elastic-Plastic Fracture Mechanics Evaluation Program for Leak-Before-Break Analysis of Nuclear Piping (원전 배관 파단전누설 평가를 위한 탄소성 파괴역학 평가 프로그램 개발)

  • Park, Jun-Geun;Huh, Nam-Su;Kim, Ye-Ji;Lee, Sang-Min
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.16 no.2
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    • pp.35-46
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    • 2020
  • In this paper, a fracture mechanics evaluation system which can be used to assess the leak-before-break (LBB) of nuclear piping is developed. Existing solutions for calculating the fracture mechanics parameters (J-integral and crack opening displacement) required for LBB evaluation were firstly presented. Then a module for calculating J-integral and COD was developed, with an additional module for predicting the critical load based on the crack driving force diagram to finally develop a fracture mechanics evaluation system. To confirm the validity of the proposed evaluation system, finite element (FE) analysis was performed, and the FE J-integral and COD results were compared with prediction results using the J-integral and COD estimations program. Furthermore, the critical load assessment module was verified by comparing the actual pipe test results (Battelle test data) with prediction results using the proposed program.

Evaluation of Material Properties for Yonggwang Nuclear Piping Systems (III) - Main Steam System - (영광원자력 배관소재의 재료물성치 평가 (III) -주증기계통-)

  • 김영진;석창성;김종욱
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.19 no.6
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    • pp.1460-1468
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    • 1995
  • The objective of this paper is to evaluate the material properties of SA106 Gr. C carbon steel and its associated weld manufactured for main steam system of Yonggwang 3,4 nuclear generating stations. A total of 43 tensile and 35 fracture toughness tests were performed and the effects of various parameters such as pipe size, crack plane orientation, test temperature, welding on material properties were discussed. Test results show that the effects of crack plane orientation, test temperature, and welding on fracture toughness were significant while the effects of pipe size, specimen orientation and test temperature on tensile properties were negligible. Especially the dependence of J-R curves on the crack plane orientation appears to be the characteristics of carbon steel.

Crack Opening Displacement Estimation for Engineering Leak-Before-Break Analyses of Pressurized Nuclear Piping (원자력 배관의 공학적 파단전누설 해석을 위한 균열열림변위 계산)

  • Huh Nam-Su;Kim Yun-Jae;Chang Yoon-Suk;Yang Jun-Seok;Choi Jae-Boons
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.10
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    • pp.1612-1620
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    • 2004
  • This study presents methods to estimate elastic-plastic crack opening displacement (COD) fur circumferential through-wall cracked pipes for the Leak-Before-Break (LBB) analysis of pressurized piping. Proposed methods are based not only on the GE/EPRI approach but also on the reference stress approach. For each approach, two different estimation schemes are given, one for the case when full stress-strain data are available and the other fur the case when only yield and ultimate tensile strengths are available. For the GE/EPRI approach a robust way of determining the Ramberg-Osgood (R-O) parameters is proposed, not only fur the case when detailed information on full stress-strain data is available but also for the case when only yield and ultimate tensile strengths are available. The COD estimates according to the GE/EPRI approach, using the R-O parameters determined from the proposed R-O fitting procedures, generally compare well with the published pipe test data. For the reference stress approach, the COD estimates according to the method based on both full stress-strain data and limited tensile properties are in good agreement with pipe test data. In conclusion, experimental validation given in the present study provides sufficient confidence in the use of the proposed method to practical LBB analyses even though when information on material's tensile properties is limited.