Impact of Revised Thermal Neutron Capture Cross Section of Carbon Stored in JENDL-4.0 on HTTR Criticality Calculation

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概要

• 論文の詳細を見る
• 2011-07-01

著者

• Goto Minoru

  Japan Atomic Energy Agency

• SHIMAKAWA Satoshi

  Japan Atomic Energy Agency

• NAKAO Yasuyuki

  Kyushu University

関連論文

• Improvement of Analysis Technology for High Temperature Gas-Cooled Reactor by Using Data Obtained in High Temperature Engineering Test Reactor
• Neutronics Calculations of HTTR with Several Nuclear Data Libraries
• Impact of Revised Thermal Neutron Capture Cross Section of Carbon Stored in JENDL-4.0 on HTTR Criticality Calculation
• Impact of Revised Thermal Neutron Capture Cross Section of Carbon Stored in JENDL-4.0 on HTTR Criticality Calculation
• Revised Procedure for Determining Large Excess Reactivity of Reactors

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