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Diffusion controlled formation of spherical carbonate concretion in muddy sedimentary matrices

GEOCHEMICAL JOURNAL, 2020, Vol.54(4), pp.233-242

2020

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The Effect of Compaction of Na-montmorillonite on the Solubility, Diffusivity, and Sorption Capability of Ions due to Specific Pore Water Chemistry

Clay Science, 2006, Vol.12(Supplement2), pp.211-216

OHE, TOSHIAKI

2006

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Effects of velocity and concentration on diffusive transport in low permeability geological systems

Applied geochemistry, 2015-12, Vol.63, p.357-365

2015

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Simple assignment of partitioning & transmutation objectives to reduce the overall repository impacts due to thermal load and nuclide migration

Progress in nuclear energy (New series), 2002-01, Vol.40 (3), p.423-430

Ohe, Toshiaki

2002

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Introduction to Radioactive Waste－Management of Radioactive Waste from Operation and Decommissioning of Nuclear and Other Facilities (8): View of the Future

Journal of the Atomic Energy Society of Japan, 2015, Vol.57(5), pp.356-361

2015

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Numerical Analysis of Uranium Solubility in Compacted Bentonite by Applying the Activity Correction for Strong Interaction between Liquid/Solid Interface

Journal of nuclear science and technology, 2002-05, Vol.39 (5), p.582-585

2002

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Geochemical Properties of Bentonite Pore Water in High-Level-Waste Repository Condition

Nuclear technology, 1997-04, Vol.118 (1), p.49-57

1997

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A method for determining both diffusion and sorption coefficients of rock medium within a few days by adopting a micro-reactor technique

Applied geochemistry, 2008-08, Vol.23 (8), p.2130-2136

2008

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LWR High Burn-Up Operation and MOX Introduction; Fuel Cycle Performance from the Viewpoint of Waste Management

Journal of nuclear science and technology, 2009-07, Vol.46 (7), p.677

2009

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放射性廃棄物概論施設の運転および廃止措置により発生する放射性廃棄物の対策: 第8回(最終回) 将来展望

日本原子力学会誌ATOMOΣ, 2015, Vol.57(5), pp.356-361

2015

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A fast and sensitive method for evaluating nuclides migration characteristics in rock medium by using micro-channel reactor concept

Physics and chemistry of the earth. Parts A/B/C, 2007, Vol.32 (1), p.463-468

2007

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Burning of MOX fuels in LWRs; fuel history effects on thermal properties of hull and end piece wastes and the repository performance

Journal of nuclear science and technology, 2012-03, Vol.49 (3), p.310-319

2012

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Thermal Impact on Geological Disposal of Hull and End Piece Wastes Resulting from High-Burn-up Operation of LWR and Introduction of MOX Fuels into LWR

Journal of nuclear science and technology, 2009-05, Vol.46 (5), p.443

2009

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LWR High Burn-Up Operation and MOX Introduction; Fuel Cycle Performance from the Viewpoint of Waste Management

Journal of nuclear science and technology, 2009-07, Vol.46 (7), p.677-689

2009

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Cesium Sorption Rate on Non-crushed Rock Measured by a New Apparatus based on a Micro-channel-reactor Concept

MRS proceedings, 2006, Vol.985, Article 0985-NN11-08

2006

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Thermal Impact on Geological Disposal of Hull and End Piece Wastes Resulting from High-Burn-up Operation of LWR and Introduction of MOX Fuels into LWR

Journal of nuclear science and technology, 2009-05, Vol.46 (5), p.443-452

2009

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Education of Nuclear Engineering in Tokai University Survives and Revives: Challenge for Encouragement to Master of Nuclear Engineers

Journal of the Atomic Energy Society of Japan, 2009, Vol.51(7), pp.546-550

2009

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The Long-Term Alteration Rate of Na-Smectite to Ca-Form in the Bentonite Deposite Evaluated by a Cation Diffusion-Convection Model

Journal of the Clay Science Society of Japan (in Japanese), 1999/06/30, Vol.38(4), pp.220-232

1999

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Moderation of Uncertainty in a Database of Sorption Coefficients (I) Factors Drawing the Scatter in Database and Data Selection

Transactions of the Atomic Energy Society of Japan, 2008, Vol.7(3), pp.194-209

2008

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Moderation of Uncertainty in a Database of Sorption Coefficients (II) Analysis of Data Scatter by Adopting Ion Exchange Model

Transactions of the Atomic Energy Society of Japan, 2008, Vol.7(3), pp.210-220

2008

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The Long-term Degradation Rate in Natural Bentonite Formations according to the Field Data

Journal of the Clay Science Society of Japan (in Japanese), 1998/08/17, Vol.38(1), pp.10-22

1998

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Numerical Analysis of Uranium Solubility in Compacted Bentonite by Applying the Activity Correction for Strong Interaction between Liquid/Solid Interface

Journal of nuclear science and technology, 2002-05, Vol.39 (5), p.582

2002

Volltextzugriff (PDF)

東海大学原子力工学科が再び立ち上がる: 原子力マイスター育成への挑戦

日本原子力学会誌ATOMOΣ, 2009, Vol.51(7), pp.546-550

2009

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Simultaneous Determination of Radionuclides in Seawater by Hydroxide Precipitation

Journal of nuclear science and technology, 1981-05, Vol.18 (5), p.360-368

1981

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The Role of Cement to be Expected in Radioactive Waste Disposal System

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1997/12/30, Vol.39(12), pp.1008-1018

1997

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Diffusion controlled formation of spherical carbonate concretion in muddy sedimentary matrices

The Effect of Compaction of Na-montmorillonite on the Solubility, Diffusivity, and Sorption Capability of Ions due to Specific Pore Water Chemistry

Effects of velocity and concentration on diffusive transport in low permeability geological systems

Simple assignment of partitioning & transmutation objectives to reduce the overall repository impacts due to thermal load and nuclide migration

Introduction to Radioactive Waste－Management of Radioactive Waste from Operation and Decommissioning of Nuclear and Other Facilities (8): View of the Future

Numerical Analysis of Uranium Solubility in Compacted Bentonite by Applying the Activity Correction for Strong Interaction between Liquid/Solid Interface

Geochemical Properties of Bentonite Pore Water in High-Level-Waste Repository Condition

A method for determining both diffusion and sorption coefficients of rock medium within a few days by adopting a micro-reactor technique

LWR High Burn-Up Operation and MOX Introduction; Fuel Cycle Performance from the Viewpoint of Waste Management

放射性廃棄物概論施設の運転および廃止措置により発生する放射性廃棄物の対策: 第8回(最終回) 将来展望

A fast and sensitive method for evaluating nuclides migration characteristics in rock medium by using micro-channel reactor concept

Burning of MOX fuels in LWRs; fuel history effects on thermal properties of hull and end piece wastes and the repository performance

Thermal Impact on Geological Disposal of Hull and End Piece Wastes Resulting from High-Burn-up Operation of LWR and Introduction of MOX Fuels into LWR

LWR High Burn-Up Operation and MOX Introduction; Fuel Cycle Performance from the Viewpoint of Waste Management

Cesium Sorption Rate on Non-crushed Rock Measured by a New Apparatus based on a Micro-channel-reactor Concept

Thermal Impact on Geological Disposal of Hull and End Piece Wastes Resulting from High-Burn-up Operation of LWR and Introduction of MOX Fuels into LWR

Education of Nuclear Engineering in Tokai University Survives and Revives: Challenge for Encouragement to Master of Nuclear Engineers

The Long-Term Alteration Rate of Na-Smectite to Ca-Form in the Bentonite Deposite Evaluated by a Cation Diffusion-Convection Model

Moderation of Uncertainty in a Database of Sorption Coefficients (I) Factors Drawing the Scatter in Database and Data Selection

Moderation of Uncertainty in a Database of Sorption Coefficients (II) Analysis of Data Scatter by Adopting Ion Exchange Model

The Long-term Degradation Rate in Natural Bentonite Formations according to the Field Data

Numerical Analysis of Uranium Solubility in Compacted Bentonite by Applying the Activity Correction for Strong Interaction between Liquid/Solid Interface

東海大学原子力工学科が再び立ち上がる: 原子力マイスター育成への挑戦

Simultaneous Determination of Radionuclides in Seawater by Hydroxide Precipitation

The Role of Cement to be Expected in Radioactive Waste Disposal System

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