摘要
C276合金是先进核电站燃料元件包壳的候选材料之一。本工作采用TRIM程序分别计算10和20 MeV质子辐照C276所产生的辐照损伤,比较分析能损、离位原子、DPA等参数分布。同时使用FISPACT-2007程序进行活化计算,对放射性活度、衰变余热及接触剂量率等参数进行了详细分析。结果表明:辐照损伤主要来自电子能损的贡献,高能质子与靶原子发生碰撞的几率较低。C276经同种能量质子辐照后,活化特性随着辐照时间的增长而增加。辐照时间相同时,高能质子会对材料产生更大的影响。本工作为后续的辐照损伤分子动力学模拟及计划开展的质子辐照实验提供支持。
C276 alloy is one of the candidate cladding materials in advanced nuclear power plants. In this work, the distributions of irradiation damage were calculated by the TRIM code about energy loss, target displacements and DPA of C276 irradiated by protons with energy of 10 and 20 MeV, and there were comparisons among them as well. The activation calculations of C276 were carried out with the FISPACT-2007 code at the same time. The activity, afterheat and contact dose rate during different cooling time after shutdown were described in detail. The result indicates that electronic energy loss is the main part of irradiation damage, high-energy protons get lower probability of collision. In the case of the same energy protons irradiation, the activation characteristics increase with increasing irradiation time. With the same irradiation time, high energy protons would have a greater impact on materials. This work will provide support for the molecular dynamics simulation and the planning of the proton irradiation project.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2009年第6期501-504,共4页
Atomic Energy Science and Technology
基金
国家重点基础研究发展计划资助项目(2007CB209803)
北京市科技新星计划资助项目(2007B058)
长江学者和创新团队发展计划资助项目(IRT0720)