An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study

doi:10.1002/pssb.202100149

	An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study
	Li, Jianyang 1,3,4; Zhang, Chonghong 4; Yang, Yitao 4; Wang, Tieshan 1; Ignacio, Martin-Bragado 2
刊名	PHYSICA STATUS SOLIDI B-BASIC SOLID STATE PHYSICS
	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.
资助项目	National Key Research and Development Program of China[2017YFB0702202] ; National Science Foundation of China[U1532262]
WOS关键词	SOLUTE-RICH CLUSTERS ; MICROSTRUCTURE EVOLUTION ; INTERATOMIC POTENTIALS ; DISLOCATION LOOPS ; ALPHA-FE ; IRON ; MODEL ; ALLOYS ; NUCLEATION ; CR
WOS研究方向	Physics
语种	英语
出版者	WILEY-V C H VERLAG GMBH
WOS记录号	WOS:000695048500001
资助机构	National Key Research and Development Program of China ; National Science Foundation of China
内容类型	期刊论文
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.