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CFD Analysis Technique Development for Wire Contact Effect of Fuel Rods Within Next Generation FBR in Japan

[+] Author Affiliations
Hironori Nakamura, Kazuhiro Oyama, Satoshi Hayakawa

Mitsubishi FBR Systems Inc., Shibuya, Japan

Tomoaki Ogata

Mitsubishi Heavy Industries Ltd., Kobe, Japan

Seiichiro Maeda, Takayuki Ozawa

Japan Atomic Energy Agency, Naka-gun, Japan

Paper No. ICONE25-66307, pp. V005T05A013; 7 pages
doi:10.1115/ICONE25-66307
From:
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5783-0
  • Copyright © 2017 by ASME

abstract

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.

Copyright © 2017 by ASME

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