Predicting the Irradiation Swelling of Austenitic and Ferritic/Martensitic Steels, Based on the Coupled Model of Machine Learning and Rate Theory

被引:7
作者
Zhu, Xiaohan [1 ,2 ]
Li, Xiaochen [1 ,2 ]
Zheng, Mingjie [1 ,2 ]
机构
[1] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Hefei Inst Phys Sci, Hefei 230031, Peoples R China
[2] Univ Sci & Technol China, Hefei 230026, Peoples R China
基金
中国国家自然科学基金;
关键词
austenitic and ferritic/martensitic steels; irradiation swelling; rate theory; machine learning; FE-CR ALLOYS; DEFECT PRODUCTION; DOSE-RATE; EVOLUTION; MIGRATION; DAMAGE; BCC; MICROSTRUCTURE; COALESCENCE; VACANCIES;
D O I
10.3390/met12040651
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
As nuclear structural materials, austenitic and ferritic/martensitic (F/M) steels will face inevitable irradiation swelling when fulfilling a role in nuclear reactors, especially under high-dose irradiation. For this work, a coupled machine learning rate theory (ML-RT) model for the swelling of austenitic and F/M steels was developed. In this model, ML was introduced to predict the steady-state irradiation swelling onset dose (D-onset), while the improved RT was developed to simulate the swelling behavior after the incubation period. More than 200 series of data on the D-onset of different structures of steel were collected for the ML prediction. The coefficient of determination (R) of the results in ML is more than 0.9. In the RT, the evolutions of the dislocation loop and void were described and calculated rather than using the fitting parameters. Cascade efficiency was employed to describe the cascade process. The coupled ML-RT model was verified with the swelling data from neutron irradiation experiments for various steels. The theoretical results of the swelling peak temperatures and swelling behavior are more accurate and reasonable, compared with those from the previous RT model. Using the ML-RT model, the swelling performance of CLAM steel under neutron irradiation of up to 180 dpa was predicted. The differences between the swelling performance of austenitic steels and F/M steels were analyzed and the differences were mainly associated with the bias. These results will be helpful for evaluating the neutron irradiation swelling behavior of candidate structural materials.
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页数:16
相关论文
共 43 条
[1]   The effect of dose rate on the response of austenitic stainless steels to neutron radiation [J].
Allen, TR ;
Cole, JI ;
Trybus, CL ;
Porter, DL ;
Tsai, H ;
Garner, F ;
Kenik, EA ;
Yoshitake, T ;
Ohta, J .
JOURNAL OF NUCLEAR MATERIALS, 2006, 348 (1-2) :148-164
[2]   The primary damage state in fcc, bcc and hcp metals as seen in molecular dynamics simulations [J].
Bacon, DJ ;
Gao, F ;
Osetsky, YN .
JOURNAL OF NUCLEAR MATERIALS, 2000, 276 (01) :1-12
[3]   CASCADE DAMAGE EFFECTS ON SWELLING OF IRRADIATED MATERIALS [J].
BULLOUGH, R ;
EYRE, BL ;
KRISHAN, K .
PROCEEDINGS OF THE ROYAL SOCIETY OF LONDON SERIES A-MATHEMATICAL PHYSICAL AND ENGINEERING SCIENCES, 1975, 346 (1644) :81-102
[4]   Void migration, coalescence and swelling in fusion materials [J].
Cottrell, GA .
FUSION ENGINEERING AND DESIGN, 2003, 66-68 :253-257
[5]   Microstructural changes of ferritic/martensitic steels after irradiation in spallation target environments [J].
Dai, Yong ;
Krsjak, Vladimir ;
Kuksenko, Viacheslav ;
Schaeublin, Robin .
JOURNAL OF NUCLEAR MATERIALS, 2018, 511 :508-522
[6]  
Diaz de la Rubia T., 1998, Journal of Computer-Aided Materials Design, V5, P243, DOI 10.1023/A:1008619610058
[7]   EFFECT OF VACANCY LOOPS ON SWELLING OF IRRADIATED MATERIALS [J].
FOREMAN, AJE ;
MAKIN, MJ .
JOURNAL OF NUCLEAR MATERIALS, 1979, 79 (01) :43-57
[8]  
Garner FA, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 4: RADIATION EFFECTS IN STRUCTURAL AND FUNCTIONAL MATERIALS FOR FISSION AND FUSION REACTORS, P33
[9]  
Garner FA, 2010, WOODHEAD PUBL SER EN, P308, DOI 10.1533/9781845699956.2.308
[10]  
Garner F.A., 1985, Effects of Radiation on Materials: Twelfth International Symposium: a Symposium, V870