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Ion irradiation enhances the mechanical performance of metallic glasses

Scripta materialia, 2010-04, Vol.62 (7), p.462-465

2010

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Fabrication of CeO2 ceramic spheres as a surrogate of nuclear fuel by an improved microwave-assisted rapid internal gelation process

Ceramics international, 2018-04, Vol.44 (6), p.6739-6746

2018

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Preparation of UC ceramic nuclear fuel microspheres by combination of an improved microwave-assisted rapid internal gelation with carbothermic reduction process

Ceramics international, 2018-10, Vol.44 (15), p.17945-17952

2018

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A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment

Nuclear materials and energy, 2021-06, Vol.27, p.101006, Article 101006

2021

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Irradiation creep and microstructural changes in an advanced ODS ferritic steel during helium implantation under stress

Journal of nuclear materials, 2009-04, Vol.386, p.143-146

2009

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An X-ray absorption spectroscopy study of an oxide dispersion strengthened steel

Journal of nuclear materials, 2007-05, Vol.362 (2-3), p.253-258

2007

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Niobium speciation at the metal/oxide interface of corroded niobium-doped Zircaloys: A X-ray absorption near-edge structure study

Corrosion science, 2008-05, Vol.50 (5), p.1313-1320

2008

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Macro and microscale mechanical testing and local electrode atom probe measurements of STIP irradiated F82H, Fe–8Cr ODS and Fe–8Cr–2W ODS

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.274-278

2011

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Irradiation creep and precipitation in a ferritic ODS steel under helium implantation

Journal of nuclear materials, 2008-02, Vol.373 (1), p.22-27

2008

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Characterisation of micromechanical properties using advanced techniques

Microscopy and microanalysis, 2012-07, Vol.18 (S2), p.764-765

2012

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Innovative production of nuclear fuel by microwave internal gelation: Heat transfer model of falling droplets

Progress in nuclear energy (New series), 2012-05, Vol.57, p.111-116

2012

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Oxide dispersion strengthened steel irradiation with helium ions

Journal of nuclear materials, 2006-06, Vol.352 (1-3), p.57-61

2006

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Nuclear material investigations by advanced analytical techniques

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2010-10, Vol.268 (20), p.3364-3370

2010

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Manufacturing of zirconia microspheres doped with erbia, yttria and ceria by internal gelation process as a part of a cermet fuel

Journal of nuclear materials, 2003-06, Vol.319, p.31-36

2003

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Cermet sphere-pac concept for inert matrix fuel

Journal of nuclear materials, 2003-06, Vol.319, p.37-43

2003

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Inert matrix fuel for the utilisation of plutonium

Progress in nuclear energy (New series), 2001, Vol.38 (3), p.301-308

2001

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Characterization of free falling drops inside a microwave cavity

2012 IEEE/MTT-S International Microwave Symposium Digest, 2012, p.1-3

2012

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Behavior of cesium implanted in zirconia based inert matrix fuel

Journal of nuclear materials, 1999-08, Vol.274 (1), p.61-65

1999

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Determination of the thermal conductivity in zirconia based inert matrix nuclear fuel by oscillating differential scanning calorimetry and laser flash

Thermochimica acta, 1998-12, Vol.323 (1), p.109-121

1998

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The influence of carbonate complexes on the solubility of zirconia: new experimental data

Progress in nuclear energy (New series), 2001, Vol.38 (3), p.443-446

2001

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Retention of iodine in yttria stabilized zirconia

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 1999-01, Vol.148 (1), p.783-786

1999

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Enhanced retention of cesium in yttria stabilised zirconia by co-implantation of iodine

Progress in nuclear energy (New series), 2001, Vol.38 (3), p.275-276

2001

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3.11 - Sphere-Pac and VIPAC Fuel

Comprehensive Nuclear Materials, 2012, p.275-312

2012

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3.25 - Modeling of Sphere-Pac Fuel

Comprehensive Nuclear Materials, 2012, p.789-817

2012

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Dalitz plot analysis for the X0 decaying into ηπ+π

Physics letters. B, 1969-08, Vol.29 (9), p.605-608

1969

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Ion irradiation enhances the mechanical performance of metallic glasses

Fabrication of CeO2 ceramic spheres as a surrogate of nuclear fuel by an improved microwave-assisted rapid internal gelation process

Preparation of UC ceramic nuclear fuel microspheres by combination of an improved microwave-assisted rapid internal gelation with carbothermic reduction process

A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment

Irradiation creep and microstructural changes in an advanced ODS ferritic steel during helium implantation under stress

An X-ray absorption spectroscopy study of an oxide dispersion strengthened steel

Niobium speciation at the metal/oxide interface of corroded niobium-doped Zircaloys: A X-ray absorption near-edge structure study

Macro and microscale mechanical testing and local electrode atom probe measurements of STIP irradiated F82H, Fe–8Cr ODS and Fe–8Cr–2W ODS

Irradiation creep and precipitation in a ferritic ODS steel under helium implantation

Characterisation of micromechanical properties using advanced techniques

Innovative production of nuclear fuel by microwave internal gelation: Heat transfer model of falling droplets

Oxide dispersion strengthened steel irradiation with helium ions

Nuclear material investigations by advanced analytical techniques

Manufacturing of zirconia microspheres doped with erbia, yttria and ceria by internal gelation process as a part of a cermet fuel

Cermet sphere-pac concept for inert matrix fuel

Inert matrix fuel for the utilisation of plutonium

Characterization of free falling drops inside a microwave cavity

Behavior of cesium implanted in zirconia based inert matrix fuel

Determination of the thermal conductivity in zirconia based inert matrix nuclear fuel by oscillating differential scanning calorimetry and laser flash

The influence of carbonate complexes on the solubility of zirconia: new experimental data

Retention of iodine in yttria stabilized zirconia

Enhanced retention of cesium in yttria stabilised zirconia by co-implantation of iodine

3.11 - Sphere-Pac and VIPAC Fuel

3.25 - Modeling of Sphere-Pac Fuel

Dalitz plot analysis for the X0 decaying into ηπ+π

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