An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study
文献类型:期刊论文
作者 | Li, Jianyang1,3,4![]() ![]() ![]() |
刊名 | PHYSICA STATUS SOLIDI B-BASIC SOLID STATE PHYSICS
![]() |
出版日期 | 2021-09-12 |
页码 | 6 |
关键词 | irradiation defects reactor pressure vessel model alloys simulations solute concentrations |
ISSN号 | 0370-1972 |
DOI | 10.1002/pssb.202100149 |
通讯作者 | Zhang, Chonghong(c.h.zhang@impcas.ac.cn) |
英文摘要 | Herein, the defect evolution in the FeCMnNi model alloy is investigated by the gray-alloy method in an object kinetic Monte Carlo (OKMC) model. Based on the parameters of the Fe-C system, the influence of Mn and Ni is implicitly considered, and the migration energy of mobile defects is modified. The number density of interstitial clusters and vacancy clusters in simulation has a good agreement with experimental results. The defect evolution features versus carbon and solutes concentration are also studied. The simulation results show that the number density of defect clusters increases with increasing carbon or solutes concentration. The average size of interstitial clusters decreases, while the average size of vacancy clusters is hardly affected by increasing impurity/solutes concentration. The defect features do not show a saturation tendency with increasing carbon/solutes concentrations. It also seems the influence of solutes concentration is more sensitive on defect features than carbon concentration in this FeCMnNi alloy. |
WOS关键词 | SOLUTE-RICH CLUSTERS ; MICROSTRUCTURE EVOLUTION ; INTERATOMIC POTENTIALS ; DISLOCATION LOOPS ; ALPHA-FE ; IRON ; MODEL ; ALLOYS ; NUCLEATION ; CR |
资助项目 | National Key Research and Development Program of China[2017YFB0702202] ; National Science Foundation of China[U1532262] |
WOS研究方向 | Physics |
语种 | 英语 |
WOS记录号 | WOS:000695048500001 |
出版者 | WILEY-V C H VERLAG GMBH |
资助机构 | National Key Research and Development Program of China ; National Science Foundation of China |
源URL | [http://119.78.100.186/handle/113462/136439] ![]() |
专题 | 中国科学院近代物理研究所 |
通讯作者 | Zhang, Chonghong |
作者单位 | 1.Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou 730000, Peoples R China 2.Univ Catolica Murcia, UCAM, Campus Los Jeronimos, E-03017 Murcia, Spain 3.Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China 4.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China |
推荐引用方式 GB/T 7714 | Li, Jianyang,Zhang, Chonghong,Yang, Yitao,et al. An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study[J]. PHYSICA STATUS SOLIDI B-BASIC SOLID STATE PHYSICS,2021:6. |
APA | Li, Jianyang,Zhang, Chonghong,Yang, Yitao,Wang, Tieshan,&Ignacio, Martin-Bragado.(2021).An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study.PHYSICA STATUS SOLIDI B-BASIC SOLID STATE PHYSICS,6. |
MLA | Li, Jianyang,et al."An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study".PHYSICA STATUS SOLIDI B-BASIC SOLID STATE PHYSICS (2021):6. |
入库方式: OAI收割
来源:近代物理研究所
浏览0
下载0
收藏0
其他版本
除非特别说明,本系统中所有内容都受版权保护,并保留所有权利。