压力管道裂纹泄漏定量技术研究

在分析泄漏产生的声发射信号衰减特性的基础上,通过压力管道裂纹泄漏试验,标定出信号的距离衰减常数,建立泄漏的声发射信号与泄漏率的关系式.在此基础上,推导出压力管道裂纹泄漏定量计算方法.试验验证表明,该方法能对压力管道裂纹泄漏进行有效的定量估计.     

压力管线缺陷声发射信号频谱特性试验

对含预制裂纹的压力管线进行液压疲劳试验,全程不间断地监测试验过程中产生的声发射信号,并对采集到的声发射信号的时程特性及其对应的频谱特性进行分析研究。结果表明,由裂纹扩展引发的声发射信号频谱集中在较低频带,由机械和摩擦等声源引起的声发射噪声信号频谱相对集中在较高频带。因此,通过声发射信号频谱分布特征可以识别声发射源的性质。     

多级温度及荷载条件下高放废物地质处置库花岗岩围岩蠕变特性研究

针对我国高放废物地质处置北山预选区花岗岩,开展了应力、温度分级加载条件下的蠕变特性试验,研究了花岗岩蠕变破坏过程中的裂纹扩展规律。试验过程中采用三维声发射定位系统,对岩石蠕变破坏过程中的裂纹扩展状态进行实时监测。试验结果表明,即使施加的应力水平低于损伤应力,岩石力学性质也会发生劣化。岩石内部微裂纹在应力的作用下不断积聚、扩展和连通,对应的声发射信号活跃,声发射事件不断增加。花岗岩稳态蠕变阶段的蠕变率受应力水平和温度的影响显著,温度和应力水平的升高加快了花岗岩裂纹扩展速度,导致花岗岩蠕变率增大。蠕变破坏过程中的声发射信号进一步印证了温度的影响,当温度由50℃升高到120℃时,稳态蠕变阶段的声发射计数率增加了近一个数量级。研究还发现,花岗岩蠕变破坏过程中试件内部分布最为广泛的声发射类型为低振幅声发射事件,与试件内部的微裂纹的产生及发展相对应,高振幅的声发射事件主要产生于试件的宏观破坏面周围。     

用声发射技术监测模拟压力管道的破裂

在力学试验研究中,采用声发射技术对已具有疲劳裂纹的核反应堆一回路模拟压力管进行加载爆破断裂的监测。利用声发射所具备的特征,研究试件在加载过程中裂纹从开裂直到断裂的动态过程。用声发射所表征的参数来解释在加载过程中各阶段的力学特征,弥补了常规力学测试方法的不足,从而观察了带有疲劳裂纹的试件其“开裂前兆-开裂-扩展-块速断裂”的全部过程,并给出各阶段的压力值。试验过程中采用微机进行实时数据处理。给出监测结果并确定出断裂位置。所得数据可用于反应堆承压构件的力学分析。     

应力腐蚀裂纹涡流检测信号的处理及形状重构

在核电站热交换管道、压力容器等关键设备结构的无损评价中,裂纹型缺陷形状的确定非常重要.采用一种小波分析方法对采集的应力腐蚀裂纹涡流检测信号进行了预处理,减少了噪声及非缺陷信号,并提取了缺陷信号特征,然后采用神经网络方法对裂纹形状进行了重构.结果表明,该方法具有快速、精确的优点.但在数据生成及训练网络时需要花费一定的时间.另外,由于神经网络方法不能重构裂纹电导率的分布情况,因此不能保证所重构裂纹的可靠性.但从涡流检测实用性的角度出发,在不考虑多裂纹等复杂情况下,神经网络方法可以用来重构自然裂纹.     

压力管道“先漏后破”评定的准则研究

以弹塑性断裂力学为基础,分别建立了轴向表面裂纹和周向表面裂纹韧带的极限失稳压力Pu和穿透裂纹的起裂压力Pc的表达式,提出了一种压力管道的"先漏后破"缺陷评定准则:即若管道表面裂纹韧带的极限失稳压力Pu低于相应穿透裂纹的起裂压力Pc,则管道会泄漏失效;若管道表面裂纹韧带的极限失稳压力Pu等于或大于相应穿透裂纹的起裂压力Pc,则管道会爆破失效.该准则得到了一些文献提供的试验数据的验证.     

碳纤维复合材料缠绕修复的压力管道断裂分析

采用耦合的有限元-无网格Galerkin数值算法,计算了碳纤维增强型复合材料缠绕修复的压力管道横向贯穿裂纹以及横向椭圆型表面裂纹前沿应力强度因子,据此分析了碳纤维增强型复合材料套袖长度对压力管道裂纹应力强度因子的影响.结果表明,本文所提算法能有效计算三维问题应力强度因子;含裂纹压力管道采用碳纤维增强型复合材料缠绕修复后...     

蒸汽发生器传热管腐蚀监测技术研究

蒸汽发生器传热管的腐蚀监测是保障核动力装置安全运行的重要问题之一.在对声发射技术原理进行介绍的基础上,采集和分析利用声发射仪对传热管进行加压实验时的声发射信号.实验结果表明:在传热管上形成微小直径穿孔性管壁腐蚀点,这种点蚀形成后,腐蚀先是向深处发展,形成尖端腐蚀,然后再向两侧延伸,逐渐形成裂纹,随着裂纹的进一步发展便形成泄漏事故;利用声发射仪对蒸汽发生器的传热管工作过程进行实时监控,可实时判断传热管材料的应力腐蚀情况,操作人员可根据声发射信号强度及其变化控制核动力装置的运行情况.     

基于ASME和RSE-M规范的含平面缺陷奥氏体不锈钢核级管道剩余寿命预测方法的数值对比研究

核级管道在加工和安装环节可能存在不同的缺陷。此外,由于核电厂运行条件的影响,管道中可能存在少量缺陷,如裂缝。需要合理预测评估含缺陷管道的剩余寿命,以便安排更换方案,避免对核电厂的效率造成严重影响。本文根据ASME和RSE-M规范,在应力强度因子计算、裂纹扩展分析和裂纹稳定性评价等环节,通过数值对比研究了含有平面缺陷的奥氏体不锈钢核级管道的剩余寿命评估方法,为类似工作提供参考。      

管道内表面非中心裂纹扩展研究

管道非中心裂纹和中心裂纹扩展规律有所不同,有必要进行研究。目的是得到管道内表面非中心裂纹的扩展规律和路径。采用有限元软件ABAQUS,建立了含非中心内表面裂纹管道的三维线弹性有限元模型,利用Paris公式分析了裂纹的扩展行为。结果是得到了管道内表面非中心裂纹在不同载荷作用下的扩展规律和路径,以及裂纹偏移角度对裂纹扩展的影响,并将计算结果和中心裂纹的分析结果相比较,研究两种裂纹在扩展上的差异。结论为在LBB分析中,泄漏裂纹计算时应考虑裂纹的偏心的影响,裂纹稳定性分析中则无须考虑裂纹偏心。     

An assessment of acoustic emission for nuclear pressure vessel monitoring

Recent research has greatly improved our understanding of the basic mechanisms of deformation and fracture that generate detectable acoustic emission signals in structural steels. A critical review of the application of acoustic emission (AE) to the fabrication, proof testing and in-service monitoring of nuclear pressure vessels is presented in the light of this improved understanding. The detectability of deformation and fracture processes in pressure vessel steels is discussed, and recommendations made for improving source location accuracy and the development of quantitative source assessment techniques.

Published data suggest that AE can make an important contribution to weld fabrication monitoring, and to the detection of defects in lower toughness materials during vessel proof testing. In high toughness materials, however, the signals generated during ductile crack growth may frequently be too weak for reliable detection. The feasibility of AE for continuous monitoring has not yet been adequately demonstrated because of high background noise levels and uncertainty about AE signal strengths from the defect growth processes that occur in service. In-service leak detection by AE shows considerable promise.

It is recommended that further tests are carried out with realistic defects, and under realistic conditions of loading (including thermal shock and fatigue) and of environment.     

Acoustic emission monitoring of ZB-1 intermediate scale vessel test

A program to develop the use of acoustic emission (AE) flaw detection methods for continuous surveillance of reactor pressure boundaries is in process in the United States. Evaluation of laboratory developed relationships for data verification and interpretation was performed by participation in a German intermediate scale vessel (ZB-1) test. The test sequence consisted of repeated blocks of a hydrostatic test followed by two sets of cyclic loading at different R-ratios. Testing was performed in cooperation with the German Materialprüfungsanstalt at the Grosskraftwerk facility in Mannheim, West Germany. This paper discusses preliminary results obtained during the first half of the test which was performed at 70°C. The AE system detected crack growth from machined flaws and also spontaneous crack growth in a fabrication weld. AE signals from cracking were consistently high amplitude and occurred at or near peak load. Crack growth rates estimated from AE data were consistent with values derived from crackopening-displacement gauges. The test produced unique and important data needed to develop reliable application of AE methods for continuous monitoring of reactor pressure systems.     

Characterisation of Al corrosion and its impact on the mechanical performance of composite cement wasteforms by the acoustic emission technique

In this study acoustic emission (AE) non-destructive method was used to evaluate the mechanical performance of cementitious wasteforms with encapsulated Al waste. AE waves generated as a result of Al corrosion in small-size blast furnace slag/ordinary Portland cement wasteforms were recorded and analysed. The basic principles of the conventional parameter-based AE approach and signal-based analysis were combined to establish a relationship between recorded AE signals and different interactions between the Al and the encapsulating cement matrix. The AE technique was shown as a potential and valuable tool for a new area of application related to monitoring and inspection of the mechanical stability of cementitious wasteforms with encapsulated metallic wastes such as Al.     

核压力管道临界裂纹长度的概率计算方法

在先漏后爆（ＬＢＢ）应用于核应力管道缺陷评定的前提下，考虑核管道承受载荷、材料流变应力和缺陷尺寸等参数的不确定性以及可能的核管道潜在失效模式，建立了含穿透裂纹核大无畏管道爆破概率的计算方法，进而得到在一定爆破概率下的临界裂纹长度。     

Progress for on-line acoustic emission monitoring of cracks in reactor systems

This paper reviews accomplishments and planned tasks for the NRC-sponsored research program concerned with “Acoustic Emission/Flaw Relationships for Inservice Monitoring of Nuclear Reactor Pressure Boundaries”. The objective of the acoustic emission (AE) monitoring program is to develop and validate the use of AE methods for continuous surveillance of reactor pressure boundaries to detect flaw growth. Topics discussed include testing AE monitoring on reactors, refinement of an AE signal identification relationship, study of slow crack growth rate effects on AE generation, and activity to produce an ASTM standard for AE monitoring and to gain ASME code acceptance of AE monitoring.     

Measurements of acoustic emission due to thermocycling of oxidized high temperature alloys

The ring down counts and energy of acoustic emission (AE) signals emitted during thermal cycling of oxidized IN-519, HASTELLOY X, and INCOLOY 800 H were measured. The HT alloys were oxidized in situ under a controlled oxidation potential defined by the H₂O/H₂ ratio. The hydrogen permeation was also continuously measured. A correlation between AE and changes of the hydrogen permeation which both occur during the thermal cycling procedure was observed. On the basis of the measurements some characteristic properties of the investigated oxide scales are derived.     

Experimental study on the application of acoustic emission during the hydraulic pressurization of a reactor pressure vessel

The investigations were aimed at demonstrating the state of the art of acoustic emission testing (AET) of reactor pressure vessels. The object under investigation was the large reactor pressure vessel of the MPA in Stuttgart, a boiling-water reactor pressure vessel, which was provided with a multitude of flaws in weld seams and in the base material. Six hydrostatic tests approximately up to the working pressure of a boiling-water reactor (71 bar) were carried out. In addition to the global multichannel locating technique, also local monitoring techniques were applied. Global location permitted a large number of different indications to be detected simultaneously. Not all of the known flaws did, however, show the expected number of AE events. On the other hand, it was possible to detect flaws previously unknown to the AE staff in some weld seams; these indications were confirmed by nondestructive testing. It was demonstrated that the locating accuracy of local monitoring using signal analysis was improved by a factor of 20 to 30 compared to global monitoring.     

Acoustic emission for on-line reactor monitoring: Results of intermediate vessel test monitoring and reactor hot functional testing

This article discusses a program designed to develop the use of acoustic emission (AE) methods for continuous surveillance to detect and evaluate flaw growth in reactor pressure boundaries. Technology developed in the laboratory for identifying AE from crack growth and for using that AE information to estimate flaw severity is now being evaluated on an intermediate vessel test and on a reactor facility.A vessel, designated ZB-1, has been tested under fatigue loading with simulated reactor conditions at Mannheim, West Germany, in collaboration with the German Materialprüfungsanstalt (MPA), Stuttgart. Fatigue cracking from machined flaws and in a fabrication weld were both detected clearly by AE.AE data were measured on a US nuclear reactor (Watts Bar, Unit 1) during hot functional preservice testing. This demonstrated that coolant flow noise is a manageable problem and that AE can be detected under operational coolant flow and temperature conditions.     

A study of the characteristics of the acoustic emission signals for condition monitoring of check valves in nuclear power plants

The objective of this study is to demonstrate that a condition-monitoring system based on acoustic emission (AE) detection can provide timely detection of check valve degradation and service aging so that maintenance or replacement can be preformed prior to the loss of safety function. This research is focused on the investigation and understanding of the capability of the acoustic emission technique to provide diagnostic information on check valve failures.AE testing for a check valve under controlled flow loop conditions was performed to detect and valve degradation such as wear and leakage due to foreign object interference. It is clearly demonstrated that the distinction of different types of failure were successful by systematically analyzing the characteristics of various AE parameters.