首页> 外文会议>ASME pressure vessels and piping conference;PVP2008 >INSIGHTS AND OBSERVATIONS ARISING FROM CURVE-FITTING THE CHARPY V-NOTCH AND TENSILE DATA CONTAINED WITHIN THE UNITED STATES' LIGHT WATER REACTOR SURVEILLANCE DATABASE
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INSIGHTS AND OBSERVATIONS ARISING FROM CURVE-FITTING THE CHARPY V-NOTCH AND TENSILE DATA CONTAINED WITHIN THE UNITED STATES' LIGHT WATER REACTOR SURVEILLANCE DATABASE

机译:曲线拟合美国轻水反应堆监测数据库中包含的片状V型缺口和拉伸数据所产生的见解和观察结果

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The effect of irradiation damage on the mechanical properties of reactor pressure vessel structures is monitored in operating nuclear reactors according to the provisions of 10 CFR Part 50 Appendix H. In these surveillance programs Charpy V-notch energy and tensile data are collected. Trends in these data have and continue to be used to identify and quantify embrittlement trends, which is a key aspect to maintaining the continued structural integrity of the operating reactor fleet. This paper presents the current results from an on-going investigation aimed at assessing the effect of different curve-fitting strategies on the insights that can be gained from these data trending activities.
机译:根据10 CFR第50部分附录H的规定,在运行中的核反应堆中监测辐照损伤对反应堆压力容器结构力学性能的影响。在这些监视程序中,收集了夏比V型缺口能和拉伸数据。这些数据的趋势已经并将继续用于识别和量化脆化趋势,这是维持在运反应堆船队的持续结构完整性的关键方面。本文介绍了正在进行的一项调查的当前结果,该调查旨在评估不同曲线拟合策略对从这些数据趋势活动中获得的见解的影响。

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