首页> 外文会议>ASME Pressure Vessels and Piping conference >DEVELOPMENT OF PROBABILISTIC FRACTURE MECHANICS ANALYSIS CODES FOR REACTOR PRESSURE VESSELS CONSIDERING RECENT EMBRITTLEMENT MODEL AND CALCULATION METHOD OF SIF - PROGRESS OF THE WORK
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DEVELOPMENT OF PROBABILISTIC FRACTURE MECHANICS ANALYSIS CODES FOR REACTOR PRESSURE VESSELS CONSIDERING RECENT EMBRITTLEMENT MODEL AND CALCULATION METHOD OF SIF - PROGRESS OF THE WORK

机译:考虑近期压痕模型和反应强度计算方法的反应堆压力容器概率断裂力学分析代码的开发

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It is widely recognized that the state of knowledge and data for the probabilistic calculations which had been proposed in the early 1980s made a conservative treatment of several key factors and models. Recently, applications of some new radiation embrittlement model, material database, calculation method of stress intensity factors and others which can improve fracture mechanics assessment of reactor pressure vessel (RPV) are introduced. This improvement on the accuracy and reliability of the probabilistic fracture mechanics (PFM) analysis necessitated changes in PFM analysis procedures and calculations. Modification and application of newly developed models and calculation methods are the main target of developing a probabilistic fracture mechanics analysis code based on the structure of existing R-PIE and VISA computer code to reflect the latest technical basis. Failure probabilities of reactor pressure vessel under pressurized thermal shock (PTS) conditions were calculated through finite difference method (FDM) and Monte Carlo simulation techniques with user friendly graphic interface. Moreover, various radiation embrittlement models and calculation methods of stress intensity factor at crack tip based on AFCEN code are applied and verified in the present work.
机译:众所周知,1980年代初期提出的概率计算的知识和数据状态保守地对待了几个关键因素和模型。最近,介绍了一些新的辐射脆化模型,材料数据库,应力强度因子的计算方法等可以改善反应堆压力容器(RPV)的断裂力学评估的应用。概率断裂力学(PFM)分析的准确性和可靠性上的这种改进使得必须对PFM分析程序和计算进行更改。新开发模型和计算方法的修改和应用是基于现有R-PIE和VISA计算机代码的结构来开发概率断裂力学分析代码以反映最新技术基础的主要目标。通过有限差分法(FDM)和具有用户友好图形界面的蒙特卡洛模拟技术,计算了压力热冲击(PTS)条件下反应堆压力容器的失效概率。此外,本文还基于AFCEN代码应用了各种辐射脆化模型和裂纹尖端应力强度因子的计算方法,并进行了验证。

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