第32卷 2012年
第2期 6月
核科学与工程
Nuclear Science and Engineering
Vol.32
No.2
Jun.2012
反应堆压力容器材料辐照脆化预测模型研究
乔建生1,2，尹世忠3，杨文！
（1.中国原子能科学研究院反应堆工程设计研究所，北京102413：
2.邢台学院初等教育学院，河北邢台054001;3,邢台学院物理系，河北邢台054001）
摘要：反应堆压力容器材料辐照脆化预测模型的研究对保证核反应堆安全运行、并预防重大灾难性事故的发生具有非常重要意义。本文基于RPV材料中Mn-Mo-Ni及Cr-Mo-V两种钢系的应用实际，分析了适用于RPV两类不同材料辐照脆化预测模型，研究了这些模型的物理思想和建模方法。首次提出了参数化模型和结构化模型的概念，充分肯定了参数化模型在反应堆压力容器材料辐照脆化预测方面的
重要作用，并对结构化模型的发展前景及深人研究所面临的间题进行了讨论。关键调：反应堆压力容器；辐照脆化；预测模型
中图分类号：TL341
文章标志码：A
文章编号：0258-0918(2012)02-0143-07
Study onmodels forRPVmaterial irradiation
embrittlementprediction
QIAO Jian-sheng'-,YIN Shi-zhong',YANG Wen
(1. Department of Reactor Engineering Research and Design, China Institute of Atom Energy. Beijing 102413, China
2, Educastional Sehool, Xingtai College, Xingtai of Hebei Prov, 054001, China: 3. Physics Department, Xingtai College, Xingtai of Hebei Prov, 054001, China)
Abstract: The model for RPV irradiation embrittlement prediction is one of the key issues for the safe and reliable operation of reactor. In this paper, starting from the Mn Mo-Ni type and Cr-Mo-V type nuclear pressure vessel material, several models for irradiation embrittlement prediction was stated and evaluated. The constituting method of the model was studied. It is the first time that the models related to parameter and structure was brought forward. The role for the model related to parameter in prediction of the RPV irradiation embrittlement in nuclear power plant was recognized. The development and the problems of the model related to structure were also thoroughly discussed in the paper.
Key words: reactor pressure vessel; irradiation embrittlement ; prediction model 收稿日期：2011-01-28；修回日期：2012-02-15
基金项目：国家重大基础研究发展计划资助项目（2011CB610503)
作者简介：乔建生（1965一），男，河北南宫人，高级讲师，材料物理与化学专业，主要从事核材料研究
143