Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated CladdingSource: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001::page 11015DOI: 10.1115/1.4041194Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: 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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| contributor author | Deng, Yangbin | |
| contributor author | Wu, Yingwei | |
| contributor author | Zhang, Dalin | |
| contributor author | Tian, Wenxi | |
| contributor author | Su, G. H. | |
| contributor author | Qiu, Suizheng | |
| date accessioned | 2019-03-17T09:41:35Z | |
| date available | 2019-03-17T09:41:35Z | |
| date copyright | 1/24/2019 12:00:00 AM | |
| date issued | 2019 | |
| identifier issn | 2332-8983 | |
| identifier other | ners_005_01_011015.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4255624 | |
| description abstract | 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. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding | |
| type | Journal Paper | |
| journal volume | 5 | |
| journal issue | 1 | |
| journal title | Journal of Nuclear Engineering and Radiation Science | |
| identifier doi | 10.1115/1.4041194 | |
| journal fristpage | 11015 | |
| journal lastpage | 011015-8 | |
| tree | Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001 | |
| contenttype | Fulltext |