ICONE11-36273 CORE AND CORE-INTERNAL DESIGN FOR INTEGRATED MODULAR WATER REACTOR (IMR)
スポンサーリンク
概要
著者
-
Kunugi Tomoaki
Kyoto University
-
YAMAMOTO Kazuhiko
The Japan Atomic Power Company
-
Matsumura Tetsuo
Central Research Institute Of Electric Power Industry
-
Hibi Koki
Mitsubishi Heavy Industries, Ltd.
-
Kanagawa Takashi
Mitsubishi Heavy Industries, Ltd.
-
Serizawa Akimi
Kyoto University
-
Hibi Koki
Mitsubishi Heavy Industries Ltd.
-
Kanagawa Takashi
Mitsubishi Heavy Industries Ltd.
-
Yamamoto Kazuhiko
The Japan Atomic Power Co.
関連論文
- Chemical Isotopic Analysis of Fission Products in PWR-MOX Spent Fuels and Computational Evaluation Using JENDL, ENDF/B, JEF, and JEFF
- Intrusive Effect of Wire Mesh Tomography on Gas-liquid Flow Measurement
- ICONE11-36075 A STUDY OF BUBBLY FLOW CHARACTERISTICS IN A VERTICAL TUBE USING WIRE MESH TOMOGRAPHY
- Analyses of Burnup at plutonium Spots in Uranium-Plutonium Mixed Oxide Fuels in Light Water Reactors by Neutron Transport and Burnup Calculations
- Isotopic Analysis of Actinides and Fission Products in LWR High-Burnup UO_2 Spent Fuels and its Comparison with Nuclide Composition Calculated Using JENDL, ENDF/B, JEF and JEFF
- Neutron and Gamma Ray Source Evaluation of LWR High Burn-up UO_2 and MOX Spent Fuels
- ICONE11-36506 DEVELOPMENT OF PACKAGE-REACTOR (2) : FEASIBILITY DESIGN FOR NUCLEAR POWER GENERATION SYSTEM
- ICONE11-36469 Development of Package-Reactor (1) : Necessity of ultra small-scale reactor as stand-alone energy supply system
- ICONE11-36273 CORE AND CORE-INTERNAL DESIGN FOR INTEGRATED MODULAR WATER REACTOR (IMR)
- Investigation of Neutron Reaction Behavior in Water-cooled FBR with MOX Fuel
- Two-Dimensional Baffle/Reflector Constants for Nodal Code in PWR Core Design
- Open Solicitation System of Research and Development Ideas in JAPC