论文

Fe-Cu合金基体损伤的分子动力学模拟研究

  • 杨文 ,
  • 贺新福
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  • 中国原子能科学研究院, 北京 102413
贺新福, 男, 1981年生, 助理研究员, 硕士

收稿日期: 2011-04-06

  修回日期: 2011-04-20

  网络出版日期: 2011-07-11

基金资助

国家重点基础研究发展计划项目2011CB610503和2007CD209801及国家自然科学基金项目10975194资助

MOLECULAR DYNAMICS SIMULATION OF MATRIX RADIATION DAMAGE IN Fe-Cu ALLOY

  • YANG Wen ,
  • HE Xin-Fu
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  • China Institute of Atomic Energy, Beijing 102413

Received date: 2011-04-06

  Revised date: 2011-04-20

  Online published: 2011-07-11

Supported by

Supported by National Basic Research Program of China (Nos.2011CB610503 and 2007CD209801) and National Natural Science Foundation of China (No.10975194)

摘要

采用分子动力学模拟了压力容器模型材料Fe-0.05Cu和Fe-0.3Cu合金的级联碰撞过程, 研究了辐照导致的缺陷构型及其特征能量、Cu的空位迁移机理、Cu含量对初始损伤的影响、辐照温度对间隙原子团簇和空位团簇的影响等. 结果表明, Cu对级联碰撞产生的缺陷数量、湮灭和复合没有明显影响, 但可降低空位迁移能. 辐照温度对团簇有明显影响.

本文引用格式

杨文 , 贺新福 . Fe-Cu合金基体损伤的分子动力学模拟研究[J]. 金属学报, 2011 , 47(7) : 954 -957 . DOI: 10.3724/SP.J.1037.2011.00207

Abstract

The reactor pressure vessel (RPV) is the highest priority key component in nuclear power plants and is considered irreplaceable. The embrittlement of RPV steels is in general thought to be caused primarily by the formation of Cu-enriched clusters, the formation of matrix damage features, and the segregation of P atoms at grain boundaries. The displacement cascades in Fe-0.05Cu and Fe-0.3Cu alloys were studied by molecular dynamics in the current work. It was found that substitutional Cu does not significantly affect the amount, annihilation and recombination of defect produced by displacement cascade but affects the vacancy migration energy significantly. The self-interstitial atoms (SIAs) clusters and vacancies clusters are formed during the displacement cascades and affected by irradiation temperature.

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