兰州大学机构库
An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study
Li, Jianyang1,2,3; Zhang, Chonghong1; Yang, Yitao1; Wang, TS(王铁山)2; Ignacio, Martin-Bragado4
2021-09
Online publication date2021-09
Source PublicationPHYSICA STATUS SOLIDI B-BASIC SOLID STATE PHYSICS   Impact Factor & Quartile Of Published Year  The Latest Impact Factor & Quartile
ISSN0370-1972
EISSN1521-3951
Volume258Issue:11
page numbers6
AbstractHerein, 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.
Keywordirradiation defects reactor pressure vessel model alloys simulations solute concentrations
PublisherWILEY-V C H VERLAG GMBH
DOI10.1002/pssb.202100149
Indexed ByEI ; SCOPUS ; SCIE
Language英语
WOS Research AreaPhysics
WOS SubjectPhysics, Condensed Matter
WOS IDWOS:000695048500001
Original Document TypeArticle ; Early Access
Citation statistics
Document Type期刊论文
Identifierhttps://ir.lzu.edu.cn/handle/262010/470596
Collection兰州大学
核科学与技术学院
Corresponding AuthorZhang, Chonghong
Affiliation
1.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China;
2.Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou 730000, Peoples R China;
3.Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China;
4.Univ Catolica Murcia, UCAM, Campus Los Jeronimos, E-03017 Murcia, Spain
First Author AffilicationSchool of Nuclear Science and Technology
Recommended Citation
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,2021,258(11).
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,258(11).
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 258.11(2021).
Files in This Item:
There are no files associated with this item.
Related Services
Recommend this item
Bookmark
Usage statistics
Export to Endnote
Altmetrics Score
Google Scholar
Similar articles in Google Scholar
[Li, Jianyang]'s Articles
[Zhang, Chonghong]'s Articles
[Yang, Yitao]'s Articles
Baidu academic
Similar articles in Baidu academic
[Li, Jianyang]'s Articles
[Zhang, Chonghong]'s Articles
[Yang, Yitao]'s Articles
Bing Scholar
Similar articles in Bing Scholar
[Li, Jianyang]'s Articles
[Zhang, Chonghong]'s Articles
[Yang, Yitao]'s Articles
Terms of Use
No data!
Social Bookmark/Share
No comment.
Items in the repository are protected by copyright, with all rights reserved, unless otherwise indicated.