Development of a FBR Fuel Bundle-duct Interaction Analysis Code-BAMBOO Analysis Model and Verification by Phenix High Burn-up Fuel Subassemblies
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概要
- 論文の詳細を見る
The bundle-duct interaction analysis code “BAMBOO” has been developed for the purpose of predicting deformation of a wire-wrapped fuel pin bundle of a fast breeder reactor (FBR). The BAMBOO code calculates helical bowing and oval-distortion of all the fuel pins in a fuel subassembly. We developed deformation models in order to precisely analyze the irradiation induced deformation by the code: a model to analyze fuel pin self-bowing induced by circumferential gradient of void swelling as well as thermal expansion, and a model to analyze dispersion of the orderly arrangement of a fuel pin bundle. We made deformation analyses of high burn-up fuel subassemblies in Phenix reactor and compared the calculated results with the post irradiation examination data of these subassemblies for the verification of these models. From the comparison we confirmed that the calculated values of the oval-distortion and bowing reasonably agreed with the PIE results if these models were used in the analysis of the code.
- 社団法人 日本原子力学会の論文
- 2005-07-25
著者
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Uwaba Tomoyuki
Japan Atomic Energy Agency
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Ito Masahiro
Japan Atomic Energy Agency
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Ukai Shigeharu
Japan Atomic Energy Agency
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PELLETIER Michel
Commissariat A l'energie Atomique
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Pelletier Michel
Commissariat A L'energie Atomique
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Ito Masahiro
Japan Nuclear Cycle Development Institute
関連論文
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- Irradiation Performance of Fast Reactor MOX Fuel Assemblies Irradiated to High Burnups
- Development of a FBR Fuel Bundle-duct Interaction Analysis Code-BAMBOO Analysis Model and Verification by Phenix High Burn-up Fuel Subassemblies
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