In this study, based on the code Fuel ROd Behavior Analysis (FROBA), a thermal–mechanical analysis code initially developed for traditional UO2-Zr fuel elements by our research group, a modified version was developed to perform the fuel performance simulation of accident tolerant fuels (ATFs), named FROBA-ATF. Compared with initial version, the cladding could be divided into arbitrary number control volumes with different materials in the new code, so it can be used to perform the calculation for multilayer coatings. In addition, a new nonrigid pellet–cladding mechanical interaction (PCMI) calculation model was established in the new code. The FROBA-ATF code was used to predict PCMI performance of two kind fuels with coated claddings, including the internal surface coating and external surface coating. The calculation result indicates that because the coating surface was close to the inner surface of the cladding where also was the PCMI surface, the absolute value of the combine pressure of internal surface-coated cladding was substantial larger than that of the external surface-coated cladding, which might be harmful the coating behavior. However, the internal surface-coated mode can provide a protection for alloy due to the isolation from direct contact with fuel pellets, which can result in a much lower equivalent stress of zirconium body during the PCMI.
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January 2019
Research-Article
Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding
Yangbin Deng,
Yangbin Deng
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Search for other works by this author on:
Yingwei Wu,
Yingwei Wu
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
e-mail: wyw810@mail.xjtu.edu.cn
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
e-mail: wyw810@mail.xjtu.edu.cn
Search for other works by this author on:
Dalin Zhang,
Dalin Zhang
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Search for other works by this author on:
Wenxi Tian,
Wenxi Tian
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
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G. H. Su,
G. H. Su
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
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Suizheng Qiu
Suizheng Qiu
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Search for other works by this author on:
Yangbin Deng
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Yingwei Wu
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
e-mail: wyw810@mail.xjtu.edu.cn
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
e-mail: wyw810@mail.xjtu.edu.cn
Dalin Zhang
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Wenxi Tian
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
G. H. Su
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Suizheng Qiu
Shaanxi Key Laboratory of Advanced Nuclear
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
Energy and Technology,
School of Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
1Corresponding author.
Manuscript received November 10, 2017; final manuscript received July 15, 2018; published online January 24, 2019. Assoc. Editor: Guoqiang Wang.
ASME J of Nuclear Rad Sci. Jan 2019, 5(1): 011015 (8 pages)
Published Online: January 24, 2019
Article history
Received:
November 10, 2017
Revised:
July 15, 2018
Citation
Deng, Y., Wu, Y., Zhang, D., Tian, W., Su, G. H., and Qiu, S. (January 24, 2019). "Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding." ASME. ASME J of Nuclear Rad Sci. January 2019; 5(1): 011015. https://doi.org/10.1115/1.4041194
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