Ninokata Hisashi | Research Lab. For Nuclear Reactors Tokyo Institute Of Technology
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関連著者
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Ninokata Hisashi
Research Lab. For Nuclear Reactors Tokyo Institute Of Technology
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NINOKATA Hisashi
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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Hotta Akitoshi
In-core Fuel Management Department Tepco Systems Corporation
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NINOKATA Hisashi
Department of Nuclear Engineering, Tokyo Institute of Technology
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Ninokata Hisashi
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Ninokata Hisashi
Tokyo Inst. Of Technol.
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SAWADA Tetsuo
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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Sawada Tetsuo
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Ishizu Tomoko
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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Yokoyama Tsugio
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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Endo Hiroshi
Nuclear Energy System Safety Div., Japan Nuclear Energy Safety Organization (JNES)
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TOKIWAI Moriyasu
Komae Lab., Central Research Institute of Electric Power Industry (CRIEPI)
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Ishizu Tomoko
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Ishizu Tomoko
Department Of Nuclear Engineering Tokyo Institute Of Technology
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KANEKO Junichi
Nuclear Eng. Dept., Tokyo Institute of Technology
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MINATO Akihiko
Advancesoft Corporation
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ARTISYUK Vladimir
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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Ricotti Marco
Department Of Nuclear Engineering Politecnico Di Milano
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Ninokata Hisashi
Res. Lab. For Nuclear Reactors Tokyo Inst. Of Technol.
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Carelli Mario
Science Aml Technology Department Westinghouse Electric Co.
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Artisyuk Vladimir
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Shirai H
Tepco Systems Corp. Tokyo
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Kumagai Yuji
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Kaneko Junichi
Nuclear Eng. Dept. Tokyo Institute Of Technology
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Kasahara Fumio
Nuclear Power Engineering Corporation
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MAIOLI Andrea
Science and Technology Department, Westinghouse Electric Co.
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Maioli Andrea
Science And Technology Department Westinghouse Electric Co.
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Tokiwai Moriyasu
Komae Lab. Central Research Institute Of Electric Power Industry (criepi)
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Doda Norihiro
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Bottoni Maurizio
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Hotta Akitoshi
In-core Fuel Management Department Toden Software Inc.
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Ninokata Hisashi
Research Laboratory Of Nuclear Reactors Tokyo Institute Of Technology
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Shirai Hiroshi
Research Laboratory Of Nuclear Reactors Tokyo Institute Of Technology
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Shimizu A
Wakasawan Energy Res. Center
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SHIMIZU Akinao
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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OHIRA Hiroaki
Japan Nuclear Cycle Development Institute
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BARCHEVTSEV Vladimir
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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KRIVENTSEV Vladimir
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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BARATTA Anthony
Nuclear Engineering Department, The Pennsylvania State University
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KASAHARA Fumio
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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TATE Katsumi
In-Core Fuel Management Department, Toden Software, Inc.
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Yokoyama Tsugio
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Tate Katsumi
In-core Fuel Management Department Toden Software Inc.
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Ohira H
Japan Nuclear Cycle Dev. Inst. Ibaraki
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Ohira Hiroaki
Japan Aerospace Exploration Agency
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Baratta Anthony
Nuclear Engineering Department The Pennsylvania State University
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Kriventsev V
Japan Nuclear Cycle Dev. Inst. Ibaraki
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Endo Hiroshi
Nuclear Energy System Safety Div. Japan Nuclear Energy Safety Organization (jnes)
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Li Rui
Research And Development Center Sumitomo Heavy Industries Ltd.
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Barchevtsev Vladimir
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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YAMAGUCHI Akinori
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
著作論文
- Numerical Studies on Dynamic Behavior of Air-Water Cross Flow Between Two Circular Interconnected Channels
- Study of the Self-Controllability for the Fast Reactor Core with High-Thermal-Conductivity Fuel
- Computational Fluid Dynamics Study of Liquid Droplet Impingement Erosion in the Inner Wall of a Bent Pipe
- PRA-Based SMA : the First Tool toward a Risk-Informed Approach to the Seismic Design of the IRIS
- Prediction of Release Rate of Burnt Sodium as Aerosol
- Analysis of an Out-of-pile Experiment for Materials Redistribution under Core Disruptive Accident Condition of Fast Breeder Reactors
- Prediction of the Equilibrium Two-Phase Flow Distributions in Inter-Connected Subchannel Systems
- Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors
- Second International Symposium on Global Environment and Nuclear Energy Systems
- Numerical Method for Simulation of Fluid Flow and Heat Transfer in Geometrically Disturbed Rod Bundles
- Numerical Study on Observed Decay Ratio of Coupled Neutronic-Thermal Hydraulic Instability in Ringhals Unit 1 under Random Noise Excitation
- An Algorithm for Attenuation of Turbulence in Particulate Flow Linked to the Fluid-dynamic Code COMMIX-M
- Development of Parallel Coupling System between Three-Dimensional Nodal Kinetic Code ENTREE and Two-Fluid Plant Simulator TRAC/BF1
- The Multi-Fluid Multi-Phase Subchannel Analysis Code KAMUI for Subassembly Accident Analysis of an LMFR
- Nonlinear Iterative Nodal Method Applied to Neutron Flux Modal Analysis