Kenta Inagaki - Academia.edu (original) (raw)
Papers by Kenta Inagaki
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...
Bulletin of the American Physical Society, 2018
Atomic Energy Society of Japan, 2016
Atomic Energy Society of Japan, 2019
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 ...
Atomic Energy Society of Japan, 2020
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.
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.
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...
The Proceedings of The Computational Mechanics Conference
Insights Concerning the Fukushima Daiichi Nuclear Accident Vol. 4
Journal of Nuclear Science and Technology
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...
Bulletin of the American Physical Society, 2018
Atomic Energy Society of Japan, 2016
Atomic Energy Society of Japan, 2019
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 ...
Atomic Energy Society of Japan, 2020
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.
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.
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...
The Proceedings of The Computational Mechanics Conference
Insights Concerning the Fukushima Daiichi Nuclear Accident Vol. 4
Journal of Nuclear Science and Technology