| Autor: |
Kazuhiro Oyama, Hironori Nakamura, Satoshi Hayakawa, Tomoaki Ogata, Seiichiro Maeda, Takayuki Ozawa |
| Rok vydání: |
2017 |
| Předmět: |
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| Zdroj: |
Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. |
| DOI: |
10.1115/icone25-66307 |
| Popis: |
Generally, the inside of a fuel subassembly of sodium cooled fast reactor (SFR) has complex geometry and this complexity makes it difficult to conduct computational fluid dynamics (CFD) utilizing cyclic boundary condition in a radial direction. However, present work has created a new modeling method which enables us to model only one rod with one wire (1-rod model) to represent periodically installed rods with wires, like an actual fuel subassembly. The axial geometry of the 1-rod model has one wire pitch length and has two extra buffer zones to reduce the influence of inlet and outlet boundary conditions. Since this 1-rod model requires low calculation load to represent flow field of a center rod in the fuel subassembly, the model allows the choice of increased number of mesh in both radial and axial directions. With this 1-rod model, three-dimensional (3D) thermal hydraulic simulation has been conducted to evaluate a peak local temperature caused by contact of a wire with the fuel rod cladding. As the coefficient of wire contact effect, the simulation obtained a value of 2.4, which means peak coefficient of fuel cladding temperature. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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