Kenta Inagaki - Academia.edu (original) (raw)

Papers by Kenta Inagaki

Research paper thumbnail of Development of zeolite column systems for treatment of molten chloride salt generated in pyro-reprocessing of nuclear fuel

Research paper thumbnail of tudy on the radioactive wastewater treatment system at Fukushima Daiichi Nuclear Power Station

Research paper thumbnail of Study on the radioactive wastewater treatment system at Fukushima Daiichi Nuclear Power Station

Research paper thumbnail of Simulating tests to investigate Fuel-Cladding Chemical Interaction in metal fuel for fast reactors

Research paper thumbnail of The Applicataion of Particle Method for Response Analysis of Concrete Cask in Earthquake

Research paper thumbnail of 高速炉におけるマイナーアクチニド変換のための金属燃料の特性化【Powered by NICT】

Research paper thumbnail of Study on the radioactive wastewater treatment system at Fukushima Daiichi Nuclear Power Station

Research paper thumbnail of Development of multiphysics particle method simulation code PHALSER and its application to various phenomena

Journal of Nuclear Science and Technology, 2021

A new particle method code called PHALSER (PHysics-based particle AnaLyzer for SEveRe accident) w... more A new particle method code called PHALSER (PHysics-based particle AnaLyzer for SEveRe accident) was developed to simulate various phenomena involving phase changes, such as the melting and solidification of materials. One of the main functions is to simulate the behavior of molten materials in a severe accident in a nuclear power plant. In PHALSER, four types of particle (fluid, solid, wall, and discrete element method (DEM) particles) are used to model various situations. The melting and solidification of materials can be simulated by transforming solid particles into fluid particles and vice versa when the melting and solidification conditions are met, respectively. A eutectic reaction can be approximately treated by defining the melting temperature as a function of material composition. A background model was also implemented in PHALSER to define the physical properties of the background, which corresponds to the void area where no particles are allocated, so that the effect of t...

Research paper thumbnail of Investigation on Hydrodynamic Effect on Eutectic Melting

Bulletin of the American Physical Society, 2018

Research paper thumbnail of Development of a multi-physics MPS code for the severe accident simulation

Atomic Energy Society of Japan, 2016

Research paper thumbnail of Simulation of decommissioning system of subdrain using an adsorption column analysis code

Atomic Energy Society of Japan, 2019

Research paper thumbnail of Mechanical models for electrical cables

A theoretical and experimental study of mechanical properties of electrical cables with multi ord... more A theoretical and experimental study of mechanical properties of electrical cables with multi order helical structure has been performed. Relations between applied deformations and local strains in ...

Research paper thumbnail of Investigation on the cooling performance of spray in the spent fuel storage facility

Atomic Energy Society of Japan, 2020

Research paper thumbnail of Reaction of Rare Earth Elements with Iron-Base Alloy

Research paper thumbnail of Electron probe microanalysis of a METAPHIX UPuZr metallic alloy fuel irradiated to 7.0 at.% burn-up

Journal of Nuclear Materials

h i g h l i g h t s Electron Probe MicroAnalysis of a UPuZr metallic fuel alloy irradiated to 7.0... more h i g h l i g h t s Electron Probe MicroAnalysis of a UPuZr metallic fuel alloy irradiated to 7.0 at.% burn-up. Significant redistribution of the fuel components along the fuel radius, nearly complete depletion of Zr in the central part of the fuel. Interactions between the fuel and the cladding with occurrence of a number of intermediary layers and migration of cladding elements to the fuel. Safe irradiation behaviour of the base alloy fuel.

Research paper thumbnail of Characterization of metallic fuel for minor actinides transmutation in fast reactor

Progress in Nuclear Energy, 2016

The METAPHIX programme is a collaboration between the Central Research Institute of Electric Powe... more The METAPHIX programme is a collaboration between the Central Research Institute of Electric Power Industry (CRIEPI, Japan) and the Joint Research Centre-Institute for Transuranium Elements (JRC-ITU) of the European Commission dedicated to investigate the safety and effectiveness of a closed nuclear fuel cycle based on Minor Actinides (MA: Np, Am, Cm) separation from spent fuel, incorporation in metal alloy fuel and transmutation in fast reactor. Nine Na-bonded experimental pins of metal alloy fuel were prepared at ITU and irradiated at the Phenix reactor (CEA, France) achieving 2.5 at.%, 7 at.% and 10 at.% burn-up. Four metal alloy compositions were irradiated: U-Pu-Zr used as fuel reference, U-Pu-Zr þ 5 wt.% MA, U-Pu-Zr þ 2 wt.% MA þ 2 wt.% Rare Earths (RE: Nd, Y, Ce, Gd), and þ5 wt.% MA þ 5 wt.% RE, respectively. RE reproduce the expected output of a pyrometallurgical reprocessing facility. Post Irradiation Examination is performed using several techniques, covering properties ranging from the macroscopic morphology of the fuel matrix to the microanalysis of phases and elemental redistribution/segregation. The irradiated fuel is characterized by many phases occurring along the fuel radius. The fuel underwent large redistribution of the fuel constituents (U, Pu, Zr) and many secondary phases are present with a variety of compositions. The distribution of phases in the irradiated fuel containing minor actinides and rare earths is essentially similar to that observed in the basic ternary alloy fuel.

Research paper thumbnail of Mechanical response of electrical cables to imposed motion

Engineering Structures, 2005

A theoretical and experimental study of mechanical properties of electrical cables with multi ord... more A theoretical and experimental study of mechanical properties of electrical cables with multi order helical structure has been performed. Relations between applied deformations and local strains in the first order helical structure have been developed. The model is then generalized with a hierarchical approach where the strains at any order helical structure are expressed as functions of strains in the upper order helix under the assumption that all components are sticking to each other. The force balance between the strains and the friction forces is considered. When the cable is exposed to small bending curvature, the slippage of the component is prevented by the frictional force. At this stage, the components of the cable behave as solid beams. Slippage occurs between the components when the tensile force in the components overcomes the frictional force. This state occurs at sufficiently large bending curvatures and results in a variable bending stiffness varying with the magnitu...

Research paper thumbnail of 1024 Visualization of Fracture Simulation Using a Particle Method

The Proceedings of The Computational Mechanics Conference

Research paper thumbnail of Multi-Physics Particle Method for the Simulation of Severe Accidents in Nuclear Power Plants

Insights Concerning the Fukushima Daiichi Nuclear Accident Vol. 4

Research paper thumbnail of Improved models of surface tension and air resistance for multiphysics particle method

Journal of Nuclear Science and Technology

Research paper thumbnail of Development of zeolite column systems for treatment of molten chloride salt generated in pyro-reprocessing of nuclear fuel

Research paper thumbnail of tudy on the radioactive wastewater treatment system at Fukushima Daiichi Nuclear Power Station

Research paper thumbnail of Study on the radioactive wastewater treatment system at Fukushima Daiichi Nuclear Power Station

Research paper thumbnail of Simulating tests to investigate Fuel-Cladding Chemical Interaction in metal fuel for fast reactors

Research paper thumbnail of The Applicataion of Particle Method for Response Analysis of Concrete Cask in Earthquake

Research paper thumbnail of 高速炉におけるマイナーアクチニド変換のための金属燃料の特性化【Powered by NICT】

Research paper thumbnail of Study on the radioactive wastewater treatment system at Fukushima Daiichi Nuclear Power Station

Research paper thumbnail of Development of multiphysics particle method simulation code PHALSER and its application to various phenomena

Journal of Nuclear Science and Technology, 2021

A new particle method code called PHALSER (PHysics-based particle AnaLyzer for SEveRe accident) w... more A new particle method code called PHALSER (PHysics-based particle AnaLyzer for SEveRe accident) was developed to simulate various phenomena involving phase changes, such as the melting and solidification of materials. One of the main functions is to simulate the behavior of molten materials in a severe accident in a nuclear power plant. In PHALSER, four types of particle (fluid, solid, wall, and discrete element method (DEM) particles) are used to model various situations. The melting and solidification of materials can be simulated by transforming solid particles into fluid particles and vice versa when the melting and solidification conditions are met, respectively. A eutectic reaction can be approximately treated by defining the melting temperature as a function of material composition. A background model was also implemented in PHALSER to define the physical properties of the background, which corresponds to the void area where no particles are allocated, so that the effect of t...

Research paper thumbnail of Investigation on Hydrodynamic Effect on Eutectic Melting

Bulletin of the American Physical Society, 2018

Research paper thumbnail of Development of a multi-physics MPS code for the severe accident simulation

Atomic Energy Society of Japan, 2016

Research paper thumbnail of Simulation of decommissioning system of subdrain using an adsorption column analysis code

Atomic Energy Society of Japan, 2019

Research paper thumbnail of Mechanical models for electrical cables

A theoretical and experimental study of mechanical properties of electrical cables with multi ord... more A theoretical and experimental study of mechanical properties of electrical cables with multi order helical structure has been performed. Relations between applied deformations and local strains in ...

Research paper thumbnail of Investigation on the cooling performance of spray in the spent fuel storage facility

Atomic Energy Society of Japan, 2020

Research paper thumbnail of Reaction of Rare Earth Elements with Iron-Base Alloy

Research paper thumbnail of Electron probe microanalysis of a METAPHIX UPuZr metallic alloy fuel irradiated to 7.0 at.% burn-up

Journal of Nuclear Materials

h i g h l i g h t s Electron Probe MicroAnalysis of a UPuZr metallic fuel alloy irradiated to 7.0... more h i g h l i g h t s Electron Probe MicroAnalysis of a UPuZr metallic fuel alloy irradiated to 7.0 at.% burn-up. Significant redistribution of the fuel components along the fuel radius, nearly complete depletion of Zr in the central part of the fuel. Interactions between the fuel and the cladding with occurrence of a number of intermediary layers and migration of cladding elements to the fuel. Safe irradiation behaviour of the base alloy fuel.

Research paper thumbnail of Characterization of metallic fuel for minor actinides transmutation in fast reactor

Progress in Nuclear Energy, 2016

The METAPHIX programme is a collaboration between the Central Research Institute of Electric Powe... more The METAPHIX programme is a collaboration between the Central Research Institute of Electric Power Industry (CRIEPI, Japan) and the Joint Research Centre-Institute for Transuranium Elements (JRC-ITU) of the European Commission dedicated to investigate the safety and effectiveness of a closed nuclear fuel cycle based on Minor Actinides (MA: Np, Am, Cm) separation from spent fuel, incorporation in metal alloy fuel and transmutation in fast reactor. Nine Na-bonded experimental pins of metal alloy fuel were prepared at ITU and irradiated at the Phenix reactor (CEA, France) achieving 2.5 at.%, 7 at.% and 10 at.% burn-up. Four metal alloy compositions were irradiated: U-Pu-Zr used as fuel reference, U-Pu-Zr þ 5 wt.% MA, U-Pu-Zr þ 2 wt.% MA þ 2 wt.% Rare Earths (RE: Nd, Y, Ce, Gd), and þ5 wt.% MA þ 5 wt.% RE, respectively. RE reproduce the expected output of a pyrometallurgical reprocessing facility. Post Irradiation Examination is performed using several techniques, covering properties ranging from the macroscopic morphology of the fuel matrix to the microanalysis of phases and elemental redistribution/segregation. The irradiated fuel is characterized by many phases occurring along the fuel radius. The fuel underwent large redistribution of the fuel constituents (U, Pu, Zr) and many secondary phases are present with a variety of compositions. The distribution of phases in the irradiated fuel containing minor actinides and rare earths is essentially similar to that observed in the basic ternary alloy fuel.

Research paper thumbnail of Mechanical response of electrical cables to imposed motion

Engineering Structures, 2005

A theoretical and experimental study of mechanical properties of electrical cables with multi ord... more A theoretical and experimental study of mechanical properties of electrical cables with multi order helical structure has been performed. Relations between applied deformations and local strains in the first order helical structure have been developed. The model is then generalized with a hierarchical approach where the strains at any order helical structure are expressed as functions of strains in the upper order helix under the assumption that all components are sticking to each other. The force balance between the strains and the friction forces is considered. When the cable is exposed to small bending curvature, the slippage of the component is prevented by the frictional force. At this stage, the components of the cable behave as solid beams. Slippage occurs between the components when the tensile force in the components overcomes the frictional force. This state occurs at sufficiently large bending curvatures and results in a variable bending stiffness varying with the magnitu...

Research paper thumbnail of 1024 Visualization of Fracture Simulation Using a Particle Method

The Proceedings of The Computational Mechanics Conference

Research paper thumbnail of Multi-Physics Particle Method for the Simulation of Severe Accidents in Nuclear Power Plants

Insights Concerning the Fukushima Daiichi Nuclear Accident Vol. 4

Research paper thumbnail of Improved models of surface tension and air resistance for multiphysics particle method

Journal of Nuclear Science and Technology