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The high burn-up structure in nuclear fuel

Materials today (Kidlington, England), 2010-12, Vol.13 (12), p.24-32

2010

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Can carbon nanotubes play a role in the field of nuclear waste management?

Environmental science & technology, 2009-03, Vol.43 (5), p.1250-1255

2009

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Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels

Journal of nuclear materials, 2010-02, Vol.397 (1), p.8-18

2010

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Characterization of alloy particles extracted from spent nuclear fuel

Journal of nuclear materials, 2012, Vol.420 (1), p.328-333

2012

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Physical and mechanical characterization of irradiated uranium dioxide with a broad burnup range and different dopants using acoustic microscopy

Journal of nuclear materials, 2017-10, Vol.494, p.322-329

2017

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Hydrogen catalytic effects of nanostructured alloy particles in spent fuel on radionuclide immobilization

Applied catalysis. B, Environmental, 2010-02, Vol.94 (1-2), p.173-178

2010

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High Frequency Acoustic Microscopy for the Determination of Porosity and Young's Modulus in High Burnup Uranium Dioxide Nuclear Fuel

IEEE transactions on nuclear science, 2016-06, Vol.63 (3), p.1520-1525

2016

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Minor actinide transmutation in fast reactor metal fuels irradiated for 120 and 360 equivalent full-power days

Journal of nuclear science and technology, 2016-07, Vol.53 (7), p.968-980

2016

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Comparative study of fission product release of homogeneous and heterogeneous high-burn up MOX fuel by Knudsen Effusion Mass Spectrometry supported by EPMA, SEM/TEM and thermal diffusivity investigations

Journal of nuclear materials, 2023-05, Vol.578, p.154340, Article 154340

2023

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Zirconate pyrochlore as a transmutation target: thermal behaviour and radiation resistance against fission fragment impact

Journal of nuclear materials, 2003-06, Vol.319 (Complete), p.59-64

2003

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Elastic properties of severely degraded fuels

Journal of nuclear materials, 2020-02, Vol.529, p.151918, Article 151918

2020

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Thermal conductivity of homogeneous and heterogeneous MOX fuel with up to 44 MWd/kgHM burn-up

Journal of nuclear materials, 2011-05, Vol.412 (1), p.129-137

2011

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Effect of burn-up on the thermal conductivity of uranium–gadolinium dioxide up to 100 GWd/tHM

Journal of nuclear materials, 2014-10, Vol.453 (1-3), p.259-268

2014

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Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy

JOM (1989), 2012-12, Vol.64 (12), p.1390-1395

2012

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Thermophysical characterization of ZrN and (Zr,Pu)N

Journal of alloys and compounds, 2009-04, Vol.473 (1), p.265-271

2009

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Helium solubility and behaviour in uranium dioxide

Journal of nuclear materials, 2009-03, Vol.385 (2), p.461-466

2009

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Effects of silica nanoparticle addition to the secondary coating of dual-coated optical fibers

Acta materialia, 2006-06, Vol.54 (10), p.2631-2636

2006

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Characterization of metallic fuel for minor actinides transmutation in fast reactor

Progress in nuclear energy (New series), 2017-01, Vol.94, p.194-201

2017

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Reductive precipitation of neptunium on iron surfaces under anaerobic conditions

Journal of nuclear materials, 2017-12, Vol.496, p.109-116

2017

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Volatile fission product behaviour during thermal annealing of irradiated UO2 fuel oxidised up to U3O8

Journal of nuclear materials, 2008-01, Vol.372 (2-3), p.215-225

2008

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On the oxidation state of UO2 nuclear fuel at a burn-up of around 100 MWd/kgHM

Journal of nuclear materials, 2005-10, Vol.345 (2-3), p.192-205

2005

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Fission product release and microstructure changes of irradiated MOX fuel at high temperatures

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.330-340

2013

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Scanning acoustic microscope for mechanical characterization and density estimation of irradiated nuclear fuel

Progress in nuclear energy (New series), 2014-04, Vol.72, p.63-66

2014

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The thermal conductivity of Nd2Zr2O7 pyrochlore and the thermal behaviour of pyrochlore-based inert matrix fuel

Journal of alloys and compounds, 2003-03, Vol.352 (1-2), p.1-5

2003

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Materials research on inert matrices: a screening study

Journal of nuclear materials, 1999-08, Vol.274 (1), p.47-53

1999

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The high burn-up structure in nuclear fuel

Can carbon nanotubes play a role in the field of nuclear waste management?

Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels

Characterization of alloy particles extracted from spent nuclear fuel

Physical and mechanical characterization of irradiated uranium dioxide with a broad burnup range and different dopants using acoustic microscopy

Hydrogen catalytic effects of nanostructured alloy particles in spent fuel on radionuclide immobilization

High Frequency Acoustic Microscopy for the Determination of Porosity and Young's Modulus in High Burnup Uranium Dioxide Nuclear Fuel

Minor actinide transmutation in fast reactor metal fuels irradiated for 120 and 360 equivalent full-power days

Comparative study of fission product release of homogeneous and heterogeneous high-burn up MOX fuel by Knudsen Effusion Mass Spectrometry supported by EPMA, SEM/TEM and thermal diffusivity investigations

Zirconate pyrochlore as a transmutation target: thermal behaviour and radiation resistance against fission fragment impact

Elastic properties of severely degraded fuels

Thermal conductivity of homogeneous and heterogeneous MOX fuel with up to 44 MWd/kgHM burn-up

Effect of burn-up on the thermal conductivity of uranium–gadolinium dioxide up to 100 GWd/tHM

Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy

Thermophysical characterization of ZrN and (Zr,Pu)N

Helium solubility and behaviour in uranium dioxide

Effects of silica nanoparticle addition to the secondary coating of dual-coated optical fibers

Characterization of metallic fuel for minor actinides transmutation in fast reactor

Reductive precipitation of neptunium on iron surfaces under anaerobic conditions

Volatile fission product behaviour during thermal annealing of irradiated UO2 fuel oxidised up to U3O8

On the oxidation state of UO2 nuclear fuel at a burn-up of around 100 MWd/kgHM

Fission product release and microstructure changes of irradiated MOX fuel at high temperatures

Scanning acoustic microscope for mechanical characterization and density estimation of irradiated nuclear fuel

The thermal conductivity of Nd2Zr2O7 pyrochlore and the thermal behaviour of pyrochlore-based inert matrix fuel

Materials research on inert matrices: a screening study

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