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Investigation of potential of vacuum-free femtosecond laser sintering for direct printing using silicon carbide nanoparticles without inorganic binder

Applied physics. A, Materials science & processing, 2023-07, Vol.129 (7), Article 498

2023

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Study on the effect of long-term high temperature irradiation on TRISO fuel

Nuclear Engineering and Technology, 2022, 54(8), , pp.2792-2800

2022

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Study on plutonium burner high temperature gas-cooled reactor in Japan – Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel

Nuclear engineering and design, 2020-02, Vol.357, p.110419, Article 110419

2020

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Research and development on high burnup HTGR fuels in JAEA

Mechanical Engineering Journal, 2020, Vol.7(3), pp.19-00571-19-00571

2020

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Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor

Journal of nuclear materials, 2008-05, Vol.376 (2), p.146-151

2008

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Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating

Mechanical Engineering Journal, 2018, Vol.5(5), pp.18-00084-18-00084

2018

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R&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR

Nuclear engineering and design, 2014-05, Vol.271, p.309-313

2014

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Development of high temperature gas-cooled reactor (HTGR) fuel in Japan

Progress in nuclear energy (New series), 2011-09, Vol.53 (7), p.788-793

2011

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Effect of Heat Treatment on TEM Microstructures of Zirconium Carbide Coating Layer in Fuel Particle for Advanced High Temperature Gas Cooled Reactor

Materials transactions, 2009-11, Vol.50 (11), p.2631-2636

2009

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高温ガス炉用耐酸化燃料要素の製造技術開発

日本原子力学会和文論文誌, 2019/03/01, Vol.18(1), pp.29-36

2019

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Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions

Journal of nuclear science and technology, 2010, Vol.47 (11), p.991

2010

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Spark plasma sintering of SiC/graphite functionally graded materials

Ceramics international, 2022-03, Vol.48 (6), p.8706-8708

2022

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TEM/STEM Observation of ZrC Coating Layer for Advanced High-Temperature Gas-Cooled Reactor Fuel, Part II

Journal of the American Ceramic Society, 2009-01, Vol.92 (1), p.197-203

2009

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TEM/STEM Observation of ZrC-Coating Layer for Advanced High-Temperature Gas-Cooled Reactor Fuel

Journal of the American Ceramic Society, 2007-12, Vol.90 (12), p.3968-3972

2007

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Feasibility study on burnable poison credit concept to HTGR fuel fabrication from core specification perspective

Annals of nuclear energy, 2021-02, Vol.151, p.107937, Article 107937

2021

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Experimental additive manufacturing of green body of SiC/Graphite functionally graded materials by stereolithography

International journal of applied ceramic technology, 2023-01, Vol.20 (1), p.261-265

2023

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Study on evaluation method of kernel migration of TRISO fuel for High Temperature Gas-cooled Reactor

Nuclear engineering and design, 2022-12, Vol.399, p.112033, Article 112033

2022

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Concepts and basic designs of various nuclear fuels (5): Fuels for High Temperature Gas-Cooled Reactor and Molten Salt Reactor

Journal of the Atomic Energy Society of Japan, 2021, Vol.63 (8), p.615-620

2021

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Microstructures of ZrC coated kernels for fuel of Pu-burner high temperature gas-cooled reactor in Japan

Journal of nuclear materials, 2019-08, Vol.522, p.32-40

2019

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Computing a Consensus Phylogeny via Leaf Removal

Journal of computational biology, 2020-02, Vol.27 (2), p.175-188

2020

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Toxicity Reduction with Total Volume Control in Nuclear Waste

Nuclear technology, 2022-02, Vol.208 (2), p.335-346

2022

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Preliminary Test Results for Post Irradiation Examination on the HTTR Fuel

Journal of nuclear science and technology, 2007-08, Vol.44 (8), p.1081-1088

2007

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Influences of the ZrC coating process and heat treatment on ZrC-coated kernels used as fuel in Pu-burner high temperature gas-cooled reactor in Japan

Journal of nuclear science and technology, 2021-01, Vol.58 (1), p.107-116

2021

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Shielding technology for upper structure of HTTR

Annals of nuclear energy, 2016-08, Vol.94, p.72-79

2016

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Study on the effect of long-term high temperature irradiation on TRISO fuel

Nuclear engineering and technology, 2022, Vol.54 (8), p.2792-2800

2022

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Investigation of potential of vacuum-free femtosecond laser sintering for direct printing using silicon carbide nanoparticles without inorganic binder

Study on the effect of long-term high temperature irradiation on TRISO fuel

Study on plutonium burner high temperature gas-cooled reactor in Japan – Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel

Research and development on high burnup HTGR fuels in JAEA

Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor

Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating

R&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR

Development of high temperature gas-cooled reactor (HTGR) fuel in Japan

Effect of Heat Treatment on TEM Microstructures of Zirconium Carbide Coating Layer in Fuel Particle for Advanced High Temperature Gas Cooled Reactor

高温ガス炉用耐酸化燃料要素の製造技術開発

Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions

Spark plasma sintering of SiC/graphite functionally graded materials

TEM/STEM Observation of ZrC Coating Layer for Advanced High-Temperature Gas-Cooled Reactor Fuel, Part II

TEM/STEM Observation of ZrC-Coating Layer for Advanced High-Temperature Gas-Cooled Reactor Fuel

Feasibility study on burnable poison credit concept to HTGR fuel fabrication from core specification perspective

Experimental additive manufacturing of green body of SiC/Graphite functionally graded materials by stereolithography

Study on evaluation method of kernel migration of TRISO fuel for High Temperature Gas-cooled Reactor

Concepts and basic designs of various nuclear fuels (5): Fuels for High Temperature Gas-Cooled Reactor and Molten Salt Reactor

Microstructures of ZrC coated kernels for fuel of Pu-burner high temperature gas-cooled reactor in Japan

Computing a Consensus Phylogeny via Leaf Removal

Toxicity Reduction with Total Volume Control in Nuclear Waste

Preliminary Test Results for Post Irradiation Examination on the HTTR Fuel

Influences of the ZrC coating process and heat treatment on ZrC-coated kernels used as fuel in Pu-burner high temperature gas-cooled reactor in Japan

Shielding technology for upper structure of HTTR

Study on the effect of long-term high temperature irradiation on TRISO fuel

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