UB Paderborn / Katalog / Suche / in CDI

Research and development on membrane IS process for hydrogen production using solar heat

International journal of hydrogen energy, 2019-07, Vol.44 (35), p.19141-19152

2019

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Corrosion resistance of structural materials in high-temperature aqueous sulfuric acids in thermochemical water-splitting iodine–sulfur process

International journal of hydrogen energy, 2013-05, Vol.38 (16), p.6577-6585

2013

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Study of container using hybrid technique for sulfuric acid decomposition of thermochemical water-splitting iodine-sulfur process

Mechanical Engineering Journal, 2020, Vol.7(3), pp.19-00377-19-00377

2020

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Characteristics of hybrid tube with Fe-high Si alloy lining by centrifugal casting for thermochemical water-splitting iodine-sulfur process

Mechanical Engineering Journal, 2016, Vol.3(3), pp.15-00619-15-00619

2016

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Recent activities in the field of nuclear materials and nuclear fuels

Journal of nuclear science and technology, 2014-05, Vol.51 (5), p.735-736

2014

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Correlation between Intergranular Corrosion and Impurities of Extra High Purity Austenitic Stainless Steels

Journal of Power and Energy Systems, 2010, Vol.4(1), pp.105-112

2010

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Intergranular Corrosion for Extra High Purity Austenitic Stainless Steel in Boiling Nitric Acid with Cr(VI)

Journal of Power and Energy Systems, 2009, Vol.3(1), pp.31-37

2009

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Corrosion resistance of structural materials in high-temperature aqueous sulfuric acids in thermochemical water-splitting iodineasulfur process

International journal of hydrogen energy, 2013-05, Vol.38 (16), p.6577-6585

2013

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Study of container using hybrid technique for sulfuric acid decomposition of thermochemical water-splitting iodine-sulfur process

Mechanical Engineering Journal, 2019, pp.19-00377

2019

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Radiation hardening and IASCC susceptibility of extra high purity austenitic stainless steel

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.887-891

2011

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Evaluation of Applicability on Multi-Axis Residual Stress Formed by Hard Sphere Indentation for Stress Corrosion Cracking Test

Journal of the Japan Institute of Metals and Materials, 2014, Vol.78(1), pp.16-22

2014

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Post-irradiation mechanical properties of austenitic alloys at temperatures below 703 K

Journal of nuclear materials, 1999-05, Vol.271, p.167-172

1999

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Study on Creep-Fatigue Life of Irradiated Austenitic Stainless Steel

JSME International Journal Series A Solid Mechanics and Material Engineering, 2002, Vol.45(1), pp.51-56

2002

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Irradiation behaviour of Precipitation Hardened Ni-base Super-alloys with EHP Grade under Multi-ion Irradiation

MRS proceedings, 2011, Vol.1298 (1), p.61-66, Article mrsf10-1298-q06-08

2011

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Identification of the constitutive equation by the indentation technique using plural indenters with different apex angles

Journal of materials research, 2001-08, Vol.16 (8), p.2283-2292

2001

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Development of Extra High Purity Stainless Steel for Advanced Reprocessing Process

Materia Japan, 2010, Vol.49(3), pp.122-124

2010

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硬球押し込みによる多軸残留応力場の応力腐食割れ試験法への適用性評価

日本金属学会誌, 2014, Vol.78(1), pp.16-22

2014

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R&D on high temperature components

Nuclear engineering and design, 2004-10, Vol.233 (1), p.211-223

2004

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R&D on high temperature components: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs

Nuclear engineering and design, 2004, Vol.233 (1-3), p.211-223

2004

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Corrosion-Resistant Material for IS Process

CO2 Free Ammonia As an Energy Carrier, 2022, p.241-251

2022

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R&D on thermal hydraulics of core and core–bottom structure

Nuclear engineering and design, 2004-10, Vol.233 (1), p.173-183

2004

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Evaluation method of thermal deformation for Fast Spectrum Light Water Reactor (FLWR)

Journal of High Pressure Institute of Japan, 2009/01/25, Vol.47(1), pp.12-17

2009

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R&D on thermal hydraulics of core and corebottom structure

Nuclear engineering and design, 2004-10, Vol.233 (1-3), p.173-183

2004

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先進再処理機器用の超高純度(EHP)ステンレス鋼の開発

まてりあ, 2010, Vol.49(3), pp.122-124

2010

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R&D on thermal hydraulics of core and core-bottom structure: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs

Nuclear engineering and design, 2004, Vol.233 (1-3), p.173-183

2004

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Research and development on membrane IS process for hydrogen production using solar heat

Corrosion resistance of structural materials in high-temperature aqueous sulfuric acids in thermochemical water-splitting iodine–sulfur process

Study of container using hybrid technique for sulfuric acid decomposition of thermochemical water-splitting iodine-sulfur process

Characteristics of hybrid tube with Fe-high Si alloy lining by centrifugal casting for thermochemical water-splitting iodine-sulfur process

Recent activities in the field of nuclear materials and nuclear fuels

Correlation between Intergranular Corrosion and Impurities of Extra High Purity Austenitic Stainless Steels

Intergranular Corrosion for Extra High Purity Austenitic Stainless Steel in Boiling Nitric Acid with Cr(VI)

Corrosion resistance of structural materials in high-temperature aqueous sulfuric acids in thermochemical water-splitting iodineasulfur process

Study of container using hybrid technique for sulfuric acid decomposition of thermochemical water-splitting iodine-sulfur process

Radiation hardening and IASCC susceptibility of extra high purity austenitic stainless steel

Evaluation of Applicability on Multi-Axis Residual Stress Formed by Hard Sphere Indentation for Stress Corrosion Cracking Test

Post-irradiation mechanical properties of austenitic alloys at temperatures below 703 K

Study on Creep-Fatigue Life of Irradiated Austenitic Stainless Steel

Irradiation behaviour of Precipitation Hardened Ni-base Super-alloys with EHP Grade under Multi-ion Irradiation

Identification of the constitutive equation by the indentation technique using plural indenters with different apex angles

Development of Extra High Purity Stainless Steel for Advanced Reprocessing Process

硬球押し込みによる多軸残留応力場の応力腐食割れ試験法への適用性評価

R&D on high temperature components

R&D on high temperature components: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs

Corrosion-Resistant Material for IS Process

R&D on thermal hydraulics of core and core–bottom structure

Evaluation method of thermal deformation for Fast Spectrum Light Water Reactor (FLWR)

R&D on thermal hydraulics of core and corebottom structure

先進再処理機器用の超高純度(EHP)ステンレス鋼の開発

R&D on thermal hydraulics of core and core-bottom structure: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs

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