A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels
A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels
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DOI：
10.1016/j.jnucmat.2012.09.012
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发表时间：
2013-02-01
影响因子：
3.1
通讯作者：
Yamamoto, T.
中科院分区：
文献类型：
--
作者：
Eason, E. D.;Odette, G. R.;Yamamoto, T.
本文提出了一个物理为基础的，经验校准的模型，用于估计反应堆压力容器钢的辐照诱导的转变温度变化，基于更广泛的数据库和更完整的理解脆化机制比早期的模型。基本的辐射损伤机制和数据库的简要说明包括在内，但重点是在模型和质量，它适合美国动力反应堆监测数据。该模型进行了比较，随机抽样的监督数据，被搁置，不用于拟合和选定的独立数据，从试验反应堆辐照，在这两种情况下显示良好的能力，预测数据，不用于校准。该模型与监督数据拟合良好，模型中包含的变量或可能包含的其他变量无显著残差趋势。(c)2012爱思唯尔有限公司版权所有。
This paper presents a physically-based, empirically calibrated model for estimating irradiation-induced transition temperature shifts in reactor pressure vessel steels, based on a broader database and more complete understanding of embrittlement mechanisms than was available for earlier models. Brief descriptions of the underlying radiation damage mechanisms and the database are included, but the emphasis is on the model and the quality of its fit to U.S. power reactor surveillance data. The model is compared to a random sample of surveillance data that were set aside and not used in fitting and to selected independent data from test reactor irradiations, in both cases showing good ability to predict data that were not used for calibration. The model is a good fit to the surveillance data, with no significant residual error trends for variables included in the model or additional variables that could be included. (c) 2012 Elsevier B.V. All rights reserved.