LBB在蠕变温度以上核级管道设计中的应用

LBB（Leak-Before-Break）技术是保证核反应堆结构安全和可靠的一种重要分析方法。对于在蠕变温度以上高温堆（如快堆）的核级管道,运用LBB分析时应考虑疲劳和蠕变对裂纹扩展的影响。本工作以法国规范RCC-MR的A16为基础、以快堆余热排放系统的一段管道为研究对象进行LBB分析,总结出一套运用于蠕变温度以上核级管道安全分析的LBB方法。经计算得到,在蠕变温度以上,蠕变对裂纹扩展的影响较大。经验证,该管道符合LBB技术对于裂纹稳定性及泄漏量可探测性的条件,满足从开始泄漏到裂纹失稳的时间要求。     

Leak-before-break and plastic collapse behaviour of statically indeterminate pipe system with circumferential crack

Much research has been carried out on Leak-Before-Break (LBB) behavior of pipes with cracks. However, most studies have been made on statically determinate pipe systems. Few studies have been made on LBB behavior of statically indeterminate pipe systems. Most pipe systems in nuclear power plants have supports and restraints, thus they can be considered as statically indeterminate pipe systems. From above points of view, LBB and plastic collapse behaviors of statically indeterminate pipe with circumferential crack and compliance were studied in this paper. A new method is proposed to analyze and evaluate the LBB and plastic collapse behavior of a statically indeterminate structure. The pipe system of which one end is clamped and the other is supported with compliance was analyzed. The main results obtained are as follows: (1) By combining the limit analysis theory and elastic–plastic fracture mechanics, the effects of crack size, compliance and fracture toughness on load deflection behaviors to failure and structural integrity of statically indeterminate pipe system have been analyzed quantitatively and easily. (2) When a crack grows in a statically indeterminate pipe before plastic collapse, load drop conditions can be derived quantitatively, as a function of J_IC, dJ/da, flow stress, crack size, pipe span length, compliance and flexural rigidity of the pipe. (3) The analytic method developed in this research is useful and convenient to evaluate the LBB and tearing instability behavior of a statically indeterminate pipe system. (4) LBB resolves easily for statically indeterminate pipes with a crack, even when it does not resolve for statically determinate pipes with the same crack. That results from the fact that bending moment redistribution during the fracture process occurs easily for statically indeterminate pipe systems, and its redistribution restrains plastic deformation of the cracked weak section.     

压力管道破前漏分析的一种简化方法

介绍了一种用于核反应堆管道和压力容器破前漏（ＬＢＢ）分析的简化方法，它主要以线弹性断裂力学的基础，将ＬＢＢ分析中应力强度因子，裂纹张开面积和泄漏率等计算以解析公式表达出来。这种方法使用方便，而且满足有关的国家标准和国际规范的要求，适用于一些应力分布和几何形状比较简单的管道和压力容器，或用于ＬＢＢ性质的近似估计。     

Approximate fracture methods for pipes — Part II: Applications

In the part I paper entitled “Approximate fracture methods for pipes — Part I, Theory” [4], five different J-estimation schemes for through-wall cracked pipes were presented. The (i) GE.EPRI method utilizes a compilation of finite-element solutions. The (ii) Paris/Tada and (iii) LBB.NRC methods utilize an interpolation between the linear elastic and rigid plastic solutions, (iv) the LBB.GE method also uses numerical solutions, and (v) the LBB.ENG uses an equivalent area method to estimate J. All five methods are very simple to use and all five give reasonable predictions of crack growth and failure in pipes. The present paper provides a comparison of some of the methods to full-scale finite-element analyses. In addition, predictions for actual pipe experiments compared to experimental data are also provided.     

Fracture mechanics evaluation of small diameter piping considering the latest experimental results

The results obtained from investigations carried out on austenitic piping of small nominal diameter (DN80 and DN50) are introduced and discussed together with their assessment using fracture mechanics methods. Essential results are summarised as following. The pipes with flaws (fatigue crack) down to a depth to a_max/t=0.51 (DN80) as well as a_max/t=0.62 (DN50) and a circumferential extension of results 2α=120° reached bending angles up to 26°. The ASME collapse load (test collapse load) was exceeded considerably and the experimental maximum load could not be reached. Failure due to a leakage or rupture did not occur in any test. The maximum crack extension was 0.69 mm (DN80, a_max/t=0.51) resp. 0.3 mm (DN50, a_max/t=0.62). The experimental maximum load can approximately be assessed by the limit analysis. The fracture mechanics approximation methods GE/EPRI and LBB/NRC calculated a/t=0.4 and 2α=120° initiation loads above the experimental maximum load for pipes containing flaws. These results confirmed the procedures for the proof of integrity of small diameter piping by updating information on load, deformation and failure behaviour of austenitic piping damaged with circumferential flaws. Using these results may formulate a final safety concept for the proof of integrity of small diameter piping by completing the current concepts.     

Ontario hydro's leak before break approach: Application to the darlington (candu) nuclear generating station a

Ontario Hydro has developed a leak before break (LBB) approach for application to the large diameter heat transport piping for Darlington NGS A as an alternative to the provision of pipewhip restraints. This approach has been applied to pipe sizes which are equal to or greater than 530 mm (21 in. NPS). The proposed LBB approach incorporates assessments at several levels to provide assurance against catastrophic rupture. A comprehensive and systematic review of pipe failure mechanisms is considered the first important step in establishing role and applicability of the LBB concept. The elements integral to the approach are those related to demonstration of crack stability utilizing fracture mechanics methods and those related to leak rate predictions and leakage detection capability. For evaluation of crack stability the J-integral/tearing modulus (J/T) method has been selected. Results from an extensive material test program from actual heat transport piping, forgings, associated welds and heat affected zones as inpur to EPFM analyses provide the J-resistance and J—T curves. The details of EPFM analyses for a straight pipe with a circumferential crack and a piping elbow with a central longitudinal throughwall crack are presented here. Additionally, results of crack opening detail, the effects of crack face pressure, the predictions of LEAK RATE code and an assessment of the leakage detection capability are presented.     

管道贯穿裂纹泄漏率预测

充分考虑入口为过冷水、两相和过热蒸汽等情况下的临界和非临界流动,对摩擦压降、拐角压降以及临界流模型Henry-Fauske中的相变起始点进行了修正,开发出破前泄漏(LBB)的管道贯穿裂纹泄漏率计算程序。与目前通用的裂纹泄漏率程序(PICEP和SQUIRT)分别就常规直管道、人工裂纹以及自然形成裂纹的泄漏率实验数据进行了对比。计算分析表明,该程序计算结果与实验结果吻合较好且精度高于PICEP和SQUIRT。此外,通过计算分析研究,获得了背压和滞止焓以及裂纹形貌(包括局部粗糙度、全局粗糙度及裂纹开口位移、裂纹拐角数目等)对泄漏率的影响规律。     

Application of LBB to high energy pipings of a pressurized water reactor in Korea

The application of the leak before break (LBB) technology to the newly constructed pressurized water reactors (PWRs) has been approved in Korea for several high energy systems that can meet rigorous acceptance criteria. The LBB application in Korea is based on the US Nuclear Regulatory Commision (USNRC) requirements. The purpose of the LBB evaluation is to eliminate the dynamic effects associated with the postulated double-ended guillotine break (DEGB) from design basis loads, as well as to eliminate pipe whip restraints and jet impingement barriers. There were several issues on the application of LBB to the primary coolant loop and the pressurizer surge line. Of concern were the material properties for the carbon steel for the primary coolant loop, estimation of the crack opening area at the pipe-to-nozzle interface considering the asymmetry, and the leakage crack size which barely meets the required margin of 2 for the surge line, etc. Some additional work was required by the safety authority to maintain the global safety of the plant at a sufficient level. This paper describes the regulatory application of LBB in Korea, and the issues encountered during the regulatory review.     

LBB和BP在核电站管道设计中的异同性分析

对LBB（破前漏）和BP（破裂排除）两种设计理念进行了比较，从材料质量要求、制造要求、应用范围、泄漏监测、裂纹分析及局部效应、全局效应等方面，对BP和LBB管道设计中的异同性进行了分析。分析结果表明：BP的“纵深防御”体系能包络LBB的主体内容；相对于LBB，BP对管道设计的要求更复杂；主冷却剂管道采用LBB和BP后的局部效应和全局效应大体相同。     

Validation of simplified fracture mechanics methods by testing of real components

The evaluation of integrity of structural components is often based on the proof of leak-before-break (LBB). Leak-before-break behaviour in piping constitutes a fail-safe condition. Which means that, during multiplied loading conditions, a defect results at first in a leakage. The crack length which leads to the leakage is smaller than the critical through-wall crack length. Simplified fracture mechanics concepts are used for the demonstration of LBB. For this the conservative, safe calculation of the critical through-wall crack length for ductile failure is necessary. To validate simplified calculation methods for circumferential cracks (flow stress concept (FSC); plastic limit load (PLL)) and for axial cracks (Battelle approach (BMI); Ruiz approach (RUIZ)) all available experiments on real structural components, especially on pipes, were analysed and evaluated by the mentioned simplified methods (approximately 460 experiments). The methods were adapted by application of correction factors, mainly on the flow stress, to result in conservative (safe) and realistic (as near as possible to the experiments) predictions. Depending on method (FSC, PLL, BMI, RUIZ), crack orientation (circumferential and axial cracks) and type of material (ferritic and austenitic material) different definitions of flow stresses were established.     

Observations on the effect of post-weld heat treatment on J-resistance curves of sa-106b seamless piping welds

Ontario Hydro has developed a leak-before-break (LBB) methodology for application to large diameter piping (21, 22 and 24 inch) Schedule 100 SA106B heat transport (HT) piping as a design alternative to pipe whip restraints and in recognition of the questionable benefits of providing such devices. Ontario Hydro's LBB approach uses elastic-plastic fracture mechanics (EPFM).In order to assess the stability of HT piping in the presence of hypothetical flaws, the value of the material J-integral associated with crack extension (J— R curve) must be known. In a material test program J-resistance curves were determined from various pipe heats and four different welding procedures that were developed by Ontario Hydro for nuclear Class 1 piping. The test program was designed to investigate and quantify the effect of various factors such as test temperature, crack plane orientation and welding effects which have an influence on fracture properties. An acceptable lower bound J-resistance curve for the piping steels and welds were obtained by machining maximum thickness specimens from the pipes and weldments and by testing side-grooved compact tension specimens. This paper addresses the effect of test temperature and post-weld heat treatment on the J-resistance curves from the welds.The fracture toughness of all the welds at 250°C was lower than that at 20°C. Welds that were post-weld heat treated showed high crack initiation toughness, J_lc, rising J-resistance curves and stable and ductible crack extension. Non post-weld heat treated welds, while remaining tough and ductile, showed comparatively lower J_Ic, and J-resistance curves at 250°C. This drop in toughness is possibly due to a dynamic strain aging mechanism evidenced by serrated load-displacement curves. The fracture toughness of non post-weld heat treated welds increased significantly after a comparable post-weld heat treatment.The test procedure was validated by comparing three test results against independent tests conducted by Materials Engineering Associates (MEA) of Lanham, Maryland. The J_Ic and J-resistance curves obtained by Ontario Hydro and MEA were comparable.     

LBB裂纹稳定性分析方法研究

破前漏（LBB）分析是一种先进的管道分析评价技术,其关键技术是裂纹的稳定性分析,决定着LBB技术的可用性。本文从核级管道的失效模式出发研究了LBB分析的裂纹稳定性分析问题,并探讨了修正J积分撕裂模量汇交方法(J-T方法)、修正极限载荷分析法以及两倍弹性斜率法的优缺点和适用范围,最后通过工程算例对不同分析方法进行检验,其结论可为我国核电站管道的LBB设计提供参考。     

Influences of the dynamic strain aging on the J–R fracture characteristics of the ferritic steels for reactor coolant piping system

The leak-before-break (LBB) design of the piping system for nuclear power plants has been based on the premise that the leakage due to the through-wall crack can be detected by using leak detection systems before a catastrophic break. The piping materials are required to have excellent J–R fracture characteristics. However, where ferritic steels for reactor coolant piping systems operate at the temperatures where dynamic strain aging (DSA) could occur, the fracture resistance could be reduced with the influence of DSA under dynamic loading. Therefore, in order to apply the LBB design concept to the piping system under seismic loading, both static and dynamic J–R characteristics must be evaluated.Materials used in this study are SA516 Gr.70 for the elbow pipe and SA508 Cl.1a for the main pipe and their welding joints. The crack extension during the dynamic and the static J–R tests was measured by the direct current potential drop (DCPD) and the compliance method, respectively. This paper describes the influences of the dynamic strain aging on the J–R fracture characteristics with the loading rate of the pipe materials and their welding joints.     

LBB管道裂纹泄漏率计算软件PICLES验证研究

管道裂纹泄漏率计算是破前漏（LBB）分析中的关键技术，采用与有效软件进行对比和与实验结果进行对比的方式，对国内自主研发的泄漏率计算软件PICLES进行验证研究。与已有成熟工程应用的国际同类软件（PICEP和SI-PICEP）对比，PICLES与其计算结果相差较小；与管道裂纹泄漏率实验结果对比，PICLES计算出的泄漏率与其相差?80.23%~?43.79%，PICLES计算的泄漏裂纹长度与实测裂纹长度相差21.84%~79.07%，说明将PICLES用于过冷水管道LBB分析具有较高的保守性。因此，PICLES可用于实际工程中的LBB分析。      

Fracture properties evaluation of carbon steel piping for main steam line

The objective of this paper is to evaluate the material properties of SA106 Gr.C carbon steel pipes and their associated welds manufactured for main steam line of Yonggwang nuclear generating station units 3 and 4.Tensile and fracture toughness tests were performed on specimens taken from actual pipes and the effect of various parameters such as the pipe size, the specimen orientation, the test temperature and the welding procedure on the material properties are discussed. Fracture toughness test results show significant crack plane orientation and test temperature dependence. An empirical equation correlating tensile and fracture toughness data is also proposed.     

Seismic loads for crack stability assessment, in a review of leak-before-break (LBB) applicability

This study was performed to define the seismic loading conditions for use in the crack stability assessment of a BWR for the applicability of the leak-before-break (LBB) criterion. The LBB has been applied to the design of Class 1 piping in Japanese light-water reactors. Crack penetrated condition with detectable leak in the LBB applicability review is classified into the Level C service condition. Here an S₁-earthquake (maximum design earthquake) is currently assumed, rather than an S₂-earthquake (extreme design earthquake). In order to justify this assumption, the frequency of an S₁-earthquake occurring during coolant leakage due to crack propagation was determined. The frequency of coolant leakage from Class 1 piping must be less than that of the Level C service condition (2.5 × 10⁻² to 1 × 10⁻⁴ per year) in order to assume that an S₁-earthquake is appropriate. Accordingly, the frequency of coolant leakage from Class 1 piping was calculated using a probabilistic fracture mechanics (PFM). The results of this analysis indicate that the frequency of coolant leakage from Class 1 piping is less than the expected occurrence of an S₁-earthquake. As the results, it is concluded that the assumption of the seismic loading employed in an LBB applicability review should be appropriate.     

Development of modified piping evaluation diagram for leak-before-break application to Korean next generation reactor

Recently, the piping evaluation diagram (PED) is accepted in nuclear industry for an efficient application of leak-before-break (LBB) concept to piping system at an initial piping design stage. The objective of this paper is to develop the modified PED, which can account for the variation of the material properties of the PED development stage and those of the assembly stage. For this purpose, a parametric study was performed to investigate the effect of stress–strain curve on the detectable leakage crack length and the effect of fracture resistance curve on the LBB allowable load. Finite element analyses were also performed to investigate the effect of stress–strain curve on the LBB allowable load. Finally, a modified PED was proposed as a function of crack length and the allowable safe shutdown earthquake load. The LBB analyses based on the modified PED are in good agreement with those based on the traditional PED. By adopting the modified PED, the variation of material properties can be considered in the LBB analysis and the computing times required for the application of LBB during the design process can be considerably reduced.     

动态载荷下奥氏体不锈钢管道LBB环向贯穿裂纹稳定性实验及理论分析方法研究

管道环向贯穿裂纹是否稳定是评判管道是否满足破前漏（LBB）设计准则的标准之一,为确保LBB技术安全可靠,对管道环向贯穿裂纹在动态载荷下的稳定性进行实验研究。采用水平冲击机对含环向贯穿裂纹的管道依次进行加载速度为1.22、2、3、4 m/s的高温不带运行压力的冲击实验,以获得各应变率下的实验极限载荷值,并与工程理论分析计算结果进行比较。分析表明:奥氏体不锈钢管道环向贯穿裂纹在动态载荷下的失效模式为塑性失稳;经实验验证,在工程中对承受动态载荷的奥氏体不锈钢管道进行LBB分析时,采用美国核管会标准审查大纲3.6.3破前漏评估程序（SRP 3.6.3）中的极限载荷理论分析方法具有较高的工程安全性,若同时选用准静态下的材料力学性能,则工程安全性更高。      

New leak detection technique using ceramic humidity sensor for water reactors

Leak-before-break (LBB) approach has been considered for its application to the main steam line (MSL) of Korean Next Generation Reactor (KNGR) — an advanced pressurized water reactor under development. Unlike the primary water leakage, the MSL leak detection must be based on principles other than radioactivity measurements. Among potential options that are being considered as indicators of leakage, it is believed that humidity at the proximity of the piping system is an effective one. A ceramic-based humidity sensor was developed, which can be qualified for LBB applications. The ceramic material, sintered and annealed MgCr₂O₄–TiO₂, is shown to increase its electrical conductivity upon water vapor adsorption without any negative impact due to gamma radiation over the entire temperature range of interest. In the plant applications, the sensor array can be positioned in the annulus between the piping and surrounding insulation. By the analysis of humidity distribution in the annulus, a leak rate of 1 l h⁻¹ can be detected within an hour when the distance between two adjacent sensors does not exceed 1 m. In order to minimize the number of signal wires, the use of AC impedance technique is shown to be advantageous. In this paper, the results of the development and the performance characterization of ceramic humidity sensor for the LBB application to the MSL of KNGR are summarized.     

Leak rates through cracks and slits in PHT pipes for LBB

The Leak Before Break (LBB) concept is widely used in the nuclear industry to eliminate the consideration of postulated double ended guillotine ruptures. This is based on the premise that a detectable leak will develop before a catastrophic break occurs. A ‘throughwall flaw’ is postulated at critical sections so that any leakage from the postulated flaw is sure to be detected. The main purpose of the present study is to develop computer codes to estimate the leakage critical flow through a postulated crack. Flow through a crack may not always attain thermodynamic equilibrium; therefore Henry's Homogeneous Non-equilibrium Model (HHNM) and a Homogeneous Frozen Model (HFM) have been adopted for the present study. Here HFM has been modified taking into account the contribution of change in liquid phase kinetic energy. According to these models, critical mass flow is expressed in terms of inlet quality and exit pressure and quality. The exit pressure is related to the inlet pressure through the cumulative effect of various pressure losses, e.g. entrance loss, friction loss and loss due to flashing. A hybrid correlation for frictional pressure drop due to surface roughness has been incorporated in the present method. Computer codes have been developed based on these models. The results obtained have been verified against published data and are found to be in good agreement. Parametric studies have been carried out to examine the effects of different physical and thermal–hydraulic parameters and to assess the extent of leakage.