Development of Fission Source Acceleration Method for Slow Convergence in Criticality Analysis by Using Matrix Eigenvector Applicable to Spent Fuel Transport Cask with Axial Burnup Profile

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概要

• 論文の詳細を見る
• Atomic Energy Society of Japanの論文
• 2003-06-25

著者

• Nomura Yasushi

  Japan Atomic Energy Research Institute

• KUROISHI Takeshi

  Japan Atomic Energy Research Institute

関連論文

• Development of Fission Source Acceleration Method for Slow Convergence in Criticality Analysis by Using Matrix Eigenvector Applicable to Spent Fuel Transport Cask with Axial Burnup Profile
• Development of Fission Source Acceleration Method for Slow Convergence in Criticality Analysis by Using Matrix Eigenvector Applicable to Spent Fuel Transport Cask with Axial Burnup Profile

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