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Additive manufacturing of silicon carbide for nuclear applications

Journal of nuclear materials, 2021-01, Vol.543, p.152577, Article 152577

2021

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Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ∼100 displacements per atom

Journal of the European Ceramic Society, 2018-04, Vol.38 (4), p.1087-1094

2018

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Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys

Journal of alloys and compounds, 2022-04, Vol.901, p.163419, Article 163419

2022

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Irradiation hardening of pure tungsten exposed to neutron irradiation

Journal of nuclear materials, 2016-11, Vol.480, p.235-243

2016

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High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces

Journal of the European Ceramic Society, 2019-07, Vol.39 (8), p.2634-2647

2019

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Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation

Journal of nuclear materials, 2016-03, Vol.470, p.278-289

2016

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Mechanisms of stored energy release in silicon carbide materials neutron-irradiated at elevated temperatures

Materials & design, 2022-02, Vol.214 (NA), p.110413, Article 110413

2022

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Equilibrium shapes and surface selection of nanostructures in 6H-SiC

Applied physics letters, 2017-04, Vol.110 (14)

2017

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Radiation-tolerant joining technologies for silicon carbide ceramics and composites

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.497-511

2014

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Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding

Journal of nuclear materials, 2020-08, Vol.536 (C), p.152203, Article 152203

2020

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Irradiation-induced chemical disordering in ceramics: The case of SiC

Journal of nuclear materials, 2022-07, Vol.565, p.153766, Article 153766

Koyanagi, Takaaki

2022

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Neutron energy spectrum influence on irradiation hardening and microstructural development of tungsten

Journal of nuclear materials, 2016-10, Vol.479 (C), p.249-254

2016

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Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials

Scripta materialia, 2016-03, Vol.114, p.74-78

2016

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Effects of neutron irradiation on mechanical properties of silicon carbide composites fabricated by nano-infiltration and transient eutectic-phase process

Journal of nuclear materials, , Vol.448 (1-3), p.478-486

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Determination of neutron irradiation temperatures of SiC using electrical resistivity method

Journal of nuclear materials, 2020-11, Vol.540 (C), p.152370, Article 152370

2020

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Irradiation-induced β to α SiC transformation at low temperature

Scientific reports, 2017-04, Vol.7 (1), p.1198-9, Article 1198

2017

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Irradiation creep of 3C–SiC and microstructural understanding of the underlying mechanisms

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.487-496

2014

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Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions

Journal of nuclear materials, 2017-10, Vol.494, p.46-54

2017

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The influence of sintering additives on the irradiation resistance of NITE SiC

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.435-439

2011

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Effect of differential swelling between fiber and matrix on the strength of irradiated SiC/SiC composites

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.S380-S383

2013

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PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron-Shielded Irradiated Tungsten

Fusion science and technology, 2019-08, Vol.75 (6), p.499-509

2019

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Surface chemistry of neutron irradiated tungsten in a high-temperature multi-material environment

Nuclear materials and energy, 2023-03, Vol.34, p.101323, Article 101323

2023

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Design and strategy for next-generation silicon carbide composites for nuclear energy

Journal of nuclear materials, 2020-11, Vol.540 (C), p.152375, Article 152375

2020

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Surface properties and dispersion behaviors of SiC nanopowders

Colloids and surfaces. A, Physicochemical and engineering aspects, 2014-12, Vol.463, p.93-100

2014

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Fiber/matrix debonding evaluation of SiCf/SiC composites using micropillar compression technique

Composites. Part B, Engineering, 2021-11, Vol.224 (C), p.109189, Article 109189

2021

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Additive manufacturing of silicon carbide for nuclear applications

Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ∼100 displacements per atom

Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys

Irradiation hardening of pure tungsten exposed to neutron irradiation

High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces

Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation

Mechanisms of stored energy release in silicon carbide materials neutron-irradiated at elevated temperatures

Equilibrium shapes and surface selection of nanostructures in 6H-SiC

Radiation-tolerant joining technologies for silicon carbide ceramics and composites

Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding

Irradiation-induced chemical disordering in ceramics: The case of SiC

Neutron energy spectrum influence on irradiation hardening and microstructural development of tungsten

Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials

Effects of neutron irradiation on mechanical properties of silicon carbide composites fabricated by nano-infiltration and transient eutectic-phase process

Determination of neutron irradiation temperatures of SiC using electrical resistivity method

Irradiation-induced β to α SiC transformation at low temperature

Irradiation creep of 3C–SiC and microstructural understanding of the underlying mechanisms

Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions

The influence of sintering additives on the irradiation resistance of NITE SiC

Effect of differential swelling between fiber and matrix on the strength of irradiated SiC/SiC composites

PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron-Shielded Irradiated Tungsten

Surface chemistry of neutron irradiated tungsten in a high-temperature multi-material environment

Design and strategy for next-generation silicon carbide composites for nuclear energy

Surface properties and dispersion behaviors of SiC nanopowders

Fiber/matrix debonding evaluation of SiCf/SiC composites using micropillar compression technique

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