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Solidification and re-melting mechanisms of SUS-B4C eutectic mixture

Journal of nuclear materials, 2021-01, Vol.543, p.152527, Article 152527

2021

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Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient

Journal of nuclear science and technology, 2021-04, Vol.58 (4), p.473-481

2021

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High temperature reaction between sea salt deposit and (U,Zr)O2 simulated corium debris

Journal of nuclear materials, 2013-11, Vol.443 (1-3), p.32-39

2013

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Sintering and characterization of ZrN and (Dy,Zr)N as surrogate materials for fast reactor nitride fuel

Journal of nuclear materials, 2014-01, Vol.444 (1-3), p.7-13

2014

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Direct in-situ temperature measurement for lamp-based heating device

Science and Technology of Advanced Materials: Methods, 2022-12, Vol.2 (1), p.50-54

2022

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High temperature reaction of multiple eutectic-component system: The case of solid metallic Zr and molten stainless steel-B4C

Materialia, 2021-12, Vol.20, p.101197, Article 101197

2021

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Chemical interaction of CsOH vapor with UO 2 and Fe-Zr melt

Journal of nuclear science and technology, 2024-08, p.1-8

2024

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Syntheses of neptunium trichloride and measurements of its melting temperature

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.477-479

2013

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Thermal expansion and self-irradiation damage in curium nitride lattice

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.66-71

2014

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Observation of Simulated Fuel Debris using Synchrotron Radiation

Transactions of the Materials Research Society of Japan, 2019/04/01, Vol.44(2), pp.61-64

2019

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Lattice thermal expansions of NpN, PuN and AmN

Journal of nuclear materials, 2008-05, Vol.376 (1), p.114-118

2008

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Experimental evaluation of solid solubility of lanthanide and transuranium nitrides into ZrN matrix

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.489-494

Takano, Masahide

2013

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Thermal expansion of TRU nitride solid solutions as fuel materials for transmutation of minor actinides

Journal of nuclear materials, 2009-05, Vol.389 (1), p.89-92

2009

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Reaction of hydrogen peroxide with uranium zirconium oxide solid solution – Zirconium hinders oxidative uranium dissolution

Journal of nuclear materials, 2017-12, Vol.497, p.54-59

2017

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Concepts and basic designs of various nuclear fuels (4): Metallic fuels for fast reactors and nitride fuels for ADS

Journal of the Atomic Energy Society of Japan, 2021, Vol.63 (7), p.541-546

2021

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Thermochemical and thermophysical properties of minor actinide compounds

Journal of nuclear materials, 2009-05, Vol.389 (1), p.23-28

2009

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Local Structure Analysis of ZrN, and Dy0.5Zr0.5N surrogate materials for fast reactor nitride fuel

Transactions of the Materials Research Society of Japan, 2017/04/01, Vol.42(2), pp.23-26

2017

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Lattice thermal expansions of (Dy, Zr)N solid solutions

Journal of alloys and compounds, 2007-07, Vol.439 (1), p.215-220

2007

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Thermal Conductivities of Zr-based Transuranium Nitride Solid Solutions

Journal of nuclear science and technology, 2011, Vol.48 (3), p.359

2011

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Thermal Conductivities of Zr-based Transuranium Nitride Solid Solutions

Journal of nuclear science and technology, 2011-03, Vol.48 (3), p.359-365

2011

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Characterization of solidified melt among materials of UO2 fuel and B4C control blade

Journal of nuclear science and technology, 2014-08, Vol.51 (7-8), p.859-875

2014

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Chemical species of cesium and iodine in condensed vaporized microparticles formed by melting nuclear fuel components with concrete materials

Environmental science--processes & impacts, 2023-07, Vol.25 (7), p.124-1212

2023

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Local structure analysis of DyN–ZrN solid solutions

Physica. B, Condensed matter, 2023-08, Vol.663, p.414960, Article 414960

2023

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Development of Behavior Analysis Code for MA Transmutation Nitride Fuel in Accelerator-Driven System

Transactions of the Atomic Energy Society of Japan, 2024, Vol.23(3), pp.74-80

2024

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Development of Behavior Analysis Code for MA Transmutation Nitride Fuel in Accelerator-Driven System

Nihon Genshiryoku Gakkai wabun ronbunshi = Transactions of the Atomic Energy Society of Japan, 2024, Vol.23 (3), p.74-80, Article J23.018

2024

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Solidification and re-melting mechanisms of SUS-B4C eutectic mixture

Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient

High temperature reaction between sea salt deposit and (U,Zr)O2 simulated corium debris

Sintering and characterization of ZrN and (Dy,Zr)N as surrogate materials for fast reactor nitride fuel

Direct in-situ temperature measurement for lamp-based heating device

High temperature reaction of multiple eutectic-component system: The case of solid metallic Zr and molten stainless steel-B4C

Chemical interaction of CsOH vapor with UO 2 and Fe-Zr melt

Syntheses of neptunium trichloride and measurements of its melting temperature

Thermal expansion and self-irradiation damage in curium nitride lattice

Observation of Simulated Fuel Debris using Synchrotron Radiation

Lattice thermal expansions of NpN, PuN and AmN

Experimental evaluation of solid solubility of lanthanide and transuranium nitrides into ZrN matrix

Thermal expansion of TRU nitride solid solutions as fuel materials for transmutation of minor actinides

Reaction of hydrogen peroxide with uranium zirconium oxide solid solution – Zirconium hinders oxidative uranium dissolution

Concepts and basic designs of various nuclear fuels (4): Metallic fuels for fast reactors and nitride fuels for ADS

Thermochemical and thermophysical properties of minor actinide compounds

Local Structure Analysis of ZrN, and Dy0.5Zr0.5N surrogate materials for fast reactor nitride fuel

Lattice thermal expansions of (Dy, Zr)N solid solutions

Thermal Conductivities of Zr-based Transuranium Nitride Solid Solutions

Thermal Conductivities of Zr-based Transuranium Nitride Solid Solutions

Characterization of solidified melt among materials of UO2 fuel and B4C control blade

Chemical species of cesium and iodine in condensed vaporized microparticles formed by melting nuclear fuel components with concrete materials

Local structure analysis of DyN–ZrN solid solutions

Development of Behavior Analysis Code for MA Transmutation Nitride Fuel in Accelerator-Driven System

Development of Behavior Analysis Code for MA Transmutation Nitride Fuel in Accelerator-Driven System

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