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首页> 外文期刊>Indian journal of engineering and materials sciences >Leak-before-break analysis of shell-nozzle junction of steam generator
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Leak-before-break analysis of shell-nozzle junction of steam generator

机译:蒸汽发生器壳-管接头的断裂前泄漏分析

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摘要

Investigations on leak-before-break analysis of shell-nozzle junction of steam generator (SG) are presented here. Steam generators are integral parts of the nuclear power plants. So, to prevent the catastrophic failure of such components nowadays, leak-before-break (LBB) concept is used. There are three levels of checking LBB behavior, namely level 1, level 2 and level 3. Level 1 is inherent in the design philosophy of ASME Sec. III, which is normally followed in the pipe design. This paper describes level 2 and level 3 LBB analysis for SG shell-nozzle junction. In level 2, crack propagation analysis of surface crack at the most critical locations of SG shell-nozzle junction was carried out, showing thereby, that crack growth is insignificant during the complete one power plant life cycle. Crack propagation analysis was conducted as defined in RCC-MR code. The methodology based on Paris law, which needs evaluation of effective triangle open K (triangle open K_(eff)) taking into account effect of plasticity and crack closure coefficient, was used. In level 3, through-wall leak size cracks (LSC) were postulated at the most critical locations and crack instability analysis was carried out under maximum credible loading conditions (e.g. earthquake). For crack instability analysis, various steps namely determination of leakage area and leak size crack (LSC) using leak-rate model, elastic-plastic fracture mechanics analysis (J-integral/tearing modulus approach) and limit load analysis (twice elastic slope method) were carried out. For the evaluation of critical load, elastic-plastic fracture mechanics analysis and for the evaluation of limit load, limit load analysis were carried out. Since no geometrical simplifications were possible for SG shell-nozzle junction, complete three-dimensional non-linear finite element analysis was performed. And, it has been proved that, because of postulated cracks, SG shell nozzle junction would not fail in ductile tearing and plastic collapse under maximum credible load that may act during a safe shutdown earthquake (SSE).
机译:此处介绍了蒸汽发生器(SG)的管壳-管口连接处断裂前泄漏分析的研究。蒸汽发生器是核电站的组成部分。因此,为了防止当今此类组件的灾难性故障,使用了先漏后漏(LBB)概念。检查LBB行为分为三个级别,即级别1,级别2和级别3。级别1是ASME Sec设计理念中固有的。 III,通常在管道设计中遵循。本文介绍了SG壳-喷嘴连接的2级和3级LBB分析。在第2级中,对SG壳-管接头的最关键位置的表面裂纹进行了裂纹扩展分析,从而表明,在整个一个电厂的生命周期中,裂纹的增长微不足道。按照RCC-MR代码中的定义进行裂纹扩展分析。使用了基于巴黎法的方法,该方法需要考虑塑性和裂纹闭合系数的影响来评估有效的三角形开口K(三角形开口K_(eff))。在第3级中,假定在最关键的位置处穿墙泄漏尺寸裂缝(LSC),并在最大可靠载荷条件下(例如地震)进行了裂缝不稳定性分析。对于裂纹不稳定性分析,可采用以下步骤进行各个步骤,即使用泄漏率模型确定泄漏面积和泄漏尺寸裂缝(LSC),弹塑性断裂力学分析(J积分/撕裂模量法)和极限载荷分析(两次弹性斜率方法)被执行。为了评估临界载荷,进行了弹塑性断裂力学分析,并且为了评估极限载荷,进行了极限载荷分析。由于SG壳-管接头的几何简化不可能,因此要进行完整的三维非线性有限元分析。并且,已经证明,由于假定的裂纹,在可能发生安全关闭地震(SSE)的最大可靠载荷下,SG壳管嘴连接处不会发生韧性撕裂和塑料塌陷。

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