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From waste to resource, nuclear rare metals as a dream of modern alchemists

Energy conversion and management, 2010-09, Vol.51 (9), p.1799-1805

2010

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Influence of boron vapor on transport behavior of deposited CsI during heating test simulating a BWR severe accident condition

Journal of nuclear materials, 2015-06, Vol.461, p.22-28

2015

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Adsorption of platinum-group metals and molybdenum onto aluminum ferrocyanide in spent fuel solution

Energy procedia, 2017-01, Vol.131, p.151-156

2017

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Irradiation behavior evaluation of oxide dispersion strengthened ferritic steel cladding tubes irradiated in JOYO

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.417-424

2013

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Reaction of Np, Am, and Cm ions with CO2 and O2 in a reaction cell in triple quadrupole inductively coupled plasma mass spectrometry

Journal of analytical atomic spectrometry, 2023-08, Vol.38 (8), p.1676-1681

2023

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Kinetic Analysis and Prediction of Thermal Decomposition Behavior of Tertiary Pyridine Resin in the Nitrate Form

Energy procedia, 2015-05, Vol.71, p.112-122

2015

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Technology readiness assessment of partitioning and transmutation in Japan and issues toward closed fuel cycle

Progress in nuclear energy (New series), 2014-07, Vol.74, p.242-263

2014

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Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior

Journal of nuclear science and technology, 2014-08, Vol.51 (7-8), p.876-885

2014

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Adsorption behaviors of trivalent actinides and lanthanides on pyridine resin in lithium chloride aqueous solution

Journal of radioanalytical and nuclear chemistry, 2013-04, Vol.296 (1), p.289-292

2013

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Adsorption behavior of VII group elements on tertiary pyridine resin in hydrochloric acid solution

Journal of radioanalytical and nuclear chemistry, 2009-11, Vol.282 (2), p.641-644

2009

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Feasibility study of the fast breeder reactor blanket as a target of plutonium denaturing and TRU transmutation for enhancement of the proliferation resistance and the actinide management in the future fuel cycle

Progress in nuclear energy (New series), 2015-07, Vol.82, p.92-97

2015

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Recovery of minor actinides from spent molten salt waste and decontamination of molten salt waste

Progress in nuclear energy (New series), 2011-09, Vol.53 (7), p.969-973

2011

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Removal of zirconium from spent fuel solution by alginate gel polymer

Progress in nuclear energy (New series), 2015-07, Vol.82, p.69-73

2015

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Restructuring and redistribution of actinides in Am-MOX fuel during the first 24 h of irradiation

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.480-488

2013

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A new back-end cycle strategy for enhancing separation, transmutation and utilization of materials (Adv.-ORIENT cycle)

Progress in nuclear energy (New series), 2008-03, Vol.50 (2), p.476-482

2008

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Thermochemical safety evaluation of tertiary pyridine resin for the application to multi-functional reprocessing process “Adv.-ORIENT cycle development”

Progress in nuclear energy (New series), 2011-09, Vol.53 (7), p.988-993

2011

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Development of a Multi-functional Reprocessing Process based on Ion-exchange Method by using Tertiary Pyridine-type Resin

Journal of nuclear science and technology, 2006-06, Vol.43 (6), p.681

2006

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Penetration behavior of water solution containing radioactive species into dried concrete/mortar and epoxy resin materials

Journal of nuclear science and technology, 2015-04, Vol.52 (4), p.580-587

2015

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Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity-Irradiation Tests of Np and Np-U Samples in the Experimental Fast Reactor JOYO (JAEA) and the Advanced Test Reactor at INL

Journal of nuclear science and technology, 2010-08, Vol.47 (8), p.661-670

2010

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Oxidation Behavior of Am-containing MOX Fuel Pellets in Air

Energy procedia, 2015, Vol.71, p.282-292

2015

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Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor

Journal of nuclear materials, 2009-03, Vol.385 (2), p.407-412

2009

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Chemical form consideration of released fission products from irradiated fast reactor fuels during overheating

Progress in nuclear energy (New series), 2015-07, Vol.82, p.86-91

2015

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Protected plutonium production at fast breeder reactor blanket – Chemical analysis of uranium-238 samples irradiated in the experimental fast reactor Joyo

Progress in nuclear energy (New series), 2012-05, Vol.57, p.125-129

2012

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Chemical Analysis of Americium Samples Irradiated under Fast Neutron Spectra

Journal of nuclear science and technology, 2008-09, Vol.45 (sup6), p.55-64

2008

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Analysis of Curium in Mixed Oxide Fuel Irradiated in the Experimental Fast Reactor JOYO for the Evaluation of Its Transmutation Behavior

Journal of nuclear science and technology, 2004-09, Vol.41 (9), p.907-914

2004

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From waste to resource, nuclear rare metals as a dream of modern alchemists

Influence of boron vapor on transport behavior of deposited CsI during heating test simulating a BWR severe accident condition

Adsorption of platinum-group metals and molybdenum onto aluminum ferrocyanide in spent fuel solution

Irradiation behavior evaluation of oxide dispersion strengthened ferritic steel cladding tubes irradiated in JOYO

Reaction of Np, Am, and Cm ions with CO2 and O2 in a reaction cell in triple quadrupole inductively coupled plasma mass spectrometry

Kinetic Analysis and Prediction of Thermal Decomposition Behavior of Tertiary Pyridine Resin in the Nitrate Form

Technology readiness assessment of partitioning and transmutation in Japan and issues toward closed fuel cycle

Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior

Adsorption behaviors of trivalent actinides and lanthanides on pyridine resin in lithium chloride aqueous solution

Adsorption behavior of VII group elements on tertiary pyridine resin in hydrochloric acid solution

Feasibility study of the fast breeder reactor blanket as a target of plutonium denaturing and TRU transmutation for enhancement of the proliferation resistance and the actinide management in the future fuel cycle

Recovery of minor actinides from spent molten salt waste and decontamination of molten salt waste

Removal of zirconium from spent fuel solution by alginate gel polymer

Restructuring and redistribution of actinides in Am-MOX fuel during the first 24 h of irradiation

A new back-end cycle strategy for enhancing separation, transmutation and utilization of materials (Adv.-ORIENT cycle)

Thermochemical safety evaluation of tertiary pyridine resin for the application to multi-functional reprocessing process “Adv.-ORIENT cycle development”

Development of a Multi-functional Reprocessing Process based on Ion-exchange Method by using Tertiary Pyridine-type Resin

Penetration behavior of water solution containing radioactive species into dried concrete/mortar and epoxy resin materials

Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity-Irradiation Tests of Np and Np-U Samples in the Experimental Fast Reactor JOYO (JAEA) and the Advanced Test Reactor at INL

Oxidation Behavior of Am-containing MOX Fuel Pellets in Air

Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor

Chemical form consideration of released fission products from irradiated fast reactor fuels during overheating

Protected plutonium production at fast breeder reactor blanket – Chemical analysis of uranium-238 samples irradiated in the experimental fast reactor Joyo

Chemical Analysis of Americium Samples Irradiated under Fast Neutron Spectra

Analysis of Curium in Mixed Oxide Fuel Irradiated in the Experimental Fast Reactor JOYO for the Evaluation of Its Transmutation Behavior

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