Impact of Revised Thermal Neutron Capture Cross Section of Carbon Stored in JENDL-4.0 on HTTR Criticality Calculation
スポンサーリンク
概要
著者
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Goto Minoru
Japan Atomic Energy Agency
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SHIMAKAWA Satoshi
Japan Atomic Energy Agency
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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