Research and validation on the numerical algorithm of mechanical module in a transient fuel rod performance code for fast reactor
•Models of irradiation behaviors for the fuel rod in LMFR like cracking-healing and PCMI have been established.•A numerical algorithm of mechanical module in fuel rod performance code for LMFR has been developed.•Accuracy and reliability of the numerical algorithm has been verified and validated by...
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| Published in: | Annals of nuclear energy Vol. 171; p. 108991 |
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| Main Authors: | , , , , , , |
| Format: | Journal Article |
| Language: | English |
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Elsevier Ltd
15.06.2022
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| ISSN: | 0306-4549, 1873-2100 |
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| Abstract | •Models of irradiation behaviors for the fuel rod in LMFR like cracking-healing and PCMI have been established.•A numerical algorithm of mechanical module in fuel rod performance code for LMFR has been developed.•Accuracy and reliability of the numerical algorithm has been verified and validated by analytical solutions and typical code results.
Mechanical performance is an important aspect for the fuel rod performance in LMFR. Operating conditions in LMFR, like large power density, high fast neutron flux and deep burnup, are hash for the fuel rod. The evolution of fuel rod behaviors is complicated and tightly coupled with each other through temperature, stress and burnup. Considering various in-pile behaviors of the fuel rod under fast neutron irradiation, the numerical iterative algorithm based on grid integration was established to deal with the complex nonlinear mechanical problem for the fuel rod in LMFR. Verification and validation have been carried out by comparing results from this algorithm with analytical solutions as well as results from typical code, which are all in good agreement with each other, proving the accuracy and reliability of this algorithm. |
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| AbstractList | •Models of irradiation behaviors for the fuel rod in LMFR like cracking-healing and PCMI have been established.•A numerical algorithm of mechanical module in fuel rod performance code for LMFR has been developed.•Accuracy and reliability of the numerical algorithm has been verified and validated by analytical solutions and typical code results.
Mechanical performance is an important aspect for the fuel rod performance in LMFR. Operating conditions in LMFR, like large power density, high fast neutron flux and deep burnup, are hash for the fuel rod. The evolution of fuel rod behaviors is complicated and tightly coupled with each other through temperature, stress and burnup. Considering various in-pile behaviors of the fuel rod under fast neutron irradiation, the numerical iterative algorithm based on grid integration was established to deal with the complex nonlinear mechanical problem for the fuel rod in LMFR. Verification and validation have been carried out by comparing results from this algorithm with analytical solutions as well as results from typical code, which are all in good agreement with each other, proving the accuracy and reliability of this algorithm. |
| ArticleNumber | 108991 |
| Author | Yang, Guangliang Wang, Peng Liao, Hailong Ding, Tao Guo, Zixuan Wang, Weixiang Chen, Hongli |
| Author_xml | – sequence: 1 givenname: Guangliang surname: Yang fullname: Yang, Guangliang organization: School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China – sequence: 2 givenname: Zixuan surname: Guo fullname: Guo, Zixuan organization: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China – sequence: 3 givenname: Peng surname: Wang fullname: Wang, Peng organization: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China – sequence: 4 givenname: Weixiang surname: Wang fullname: Wang, Weixiang organization: School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China – sequence: 5 givenname: Hailong surname: Liao fullname: Liao, Hailong organization: School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China – sequence: 6 givenname: Tao surname: Ding fullname: Ding, Tao organization: School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China – sequence: 7 givenname: Hongli surname: Chen fullname: Chen, Hongli email: hlchen1@ustc.edu.cn organization: School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China |
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| Keywords | SAS LWR PSI PCMI USTC ITU KMC-Fuel(tra) In-pile behaviors PDS-XADS LBE LMFR Mechanical analysis Fuel rod performance code FFTF JAERI CIAE MIT PNNL FAST TREAT BPJ ANL Numerical algorithm |
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| Snippet | •Models of irradiation behaviors for the fuel rod in LMFR like cracking-healing and PCMI have been established.•A numerical algorithm of mechanical module in... |
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| SubjectTerms | Fuel rod performance code In-pile behaviors LMFR Mechanical analysis Numerical algorithm |
| Title | Research and validation on the numerical algorithm of mechanical module in a transient fuel rod performance code for fast reactor |
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