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Fission gas release from UO2 nuclear fuel: A review

Journal of nuclear materials, 2019-01, Vol.513, p.310-345

2019

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Fabrication and characterization of (U, Am)O2−x transmutation targets

Journal of nuclear materials, 2012-02, Vol.421 (1-3), p.80-88

2012

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Bulk-nanocrystalline oxide nuclear fuels – An innovative material option for increasing fission gas retention, plasticity and radiation-tolerance

Journal of nuclear materials, 2012-03, Vol.422 (1-3), p.27-44

2012

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Synthesis of nc-UO2 by controlled precipitation in aqueous phase

Journal of nuclear materials, 2016-08, Vol.477, p.298-304

2016

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Crystal size effect on the compressibility of nano-crystalline uranium dioxide

Journal of nuclear materials, 2013-04, Vol.435 (1-3), p.123-127

2013

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Oxygen stoichiometry shift of irradiated LWR-fuels at high burn-ups: Review of data and alternative interpretation of recently published results

Journal of nuclear materials, 2008-03, Vol.375 (1), p.8-25

2008

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Thermal recovery and lattice expansion of self-irradiated U0.80Am0.20O2−x, an in situ high temperature x-ray diffraction study

Journal of solid state chemistry, 2013-03, Vol.199, p.334-337

2013

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Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up

Journal of nuclear materials, 2005-11, Vol.346 (2-3), p.131-144

2005

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Lattice parameter changes associated with the rim-structure formation in high burn-up UO2 fuels by micro x-ray diffraction

Journal of nuclear materials, 2000-10, Vol.281 (2-3), p.146-162

2000

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In situ high temperature X-ray diffraction study of UO2 nanoparticles

Journal of materials science, 2011-11, Vol.46 (22), p.7247-7252

2011

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Laser melting of nano-crystalline uranium dioxide

Progress in nuclear energy (New series), 2014-04, Vol.72, p.11-16

2014

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Stereological evolution of the rim structure in PWR-fuels at prolonged irradiation: Dependencies with burn-up and temperature

Journal of nuclear materials, 2006-08, Vol.354 (1), p.66-84

2006

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Lattice contraction in the rim zone as controlled by recrystallization: Additional evidence

Journal of nuclear materials, 2008-01, Vol.372 (2), p.416-420

2008

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Room-temperature microindentation behaviour of LWR-fuels, part 1: fuel microhardness

Journal of nuclear materials, 2003-11, Vol.322 (2), p.204-216

2003

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Formation of the rim structure in high burnup fuel

Journal of nuclear materials, 1997-09, Vol.248, p.170-179

1997

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Comments on the threshold porosity for fission gas release in high burn-up fuels

Journal of nuclear materials, 2004-06, Vol.328 (1), p.67-70

2004

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Fabrication and characterization of (U, Am)O 2− x transmutation targets

Journal of nuclear materials, 2012-02, Vol.421 (1), p.80-88

2012

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Fission gas release from UO^sub 2^ nuclear fuel: A review

Journal of nuclear materials, 2019-01, Vol.513, p.310

2019

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Phase characterisation of simulated high burn-up UO2 fuel

Journal of alloys and compounds, 1998-06, Vol.271-273, p.610-615

1998

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Bulk and Young's modulus of doped UO2 by synchrotron diffraction under high pressure and Knoop indentation

Journal of nuclear materials, 2004-01, Vol.324 (2-3), p.189-197

2004

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High burn-up rim structure: evidences that xenon-depletion, pore formation and grain subdivision start at different local burn-ups

Journal of nuclear materials, 1998-08, Vol.256 (2), p.189-196

1998

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Nanocrystalline ZrO2 ceramics with idealized macropores

Journal of the European Ceramic Society, 2008, Vol.28 (9), p.1783-1791

2008

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Fabrication and characterization of (U, Am)O2-x transmutatio

Journal of nuclear materials, 2012, Vol.421 (1-3), p.80-88

2012

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Fractal analysis of high burn-up structures in UO2

Chaos, solitons and fractals, 2004-03, Vol.19 (4), p.731-737

2004

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In situ high temperature X-ray diffraction study of U[O.sub.2] nanoparticles

Journal of materials science, 2011-11, Vol.46 (22), p.7247

2011

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Fission gas release from UO2 nuclear fuel: A review

Fabrication and characterization of (U, Am)O2−x transmutation targets

Bulk-nanocrystalline oxide nuclear fuels – An innovative material option for increasing fission gas retention, plasticity and radiation-tolerance

Synthesis of nc-UO2 by controlled precipitation in aqueous phase

Crystal size effect on the compressibility of nano-crystalline uranium dioxide

Oxygen stoichiometry shift of irradiated LWR-fuels at high burn-ups: Review of data and alternative interpretation of recently published results

Thermal recovery and lattice expansion of self-irradiated U0.80Am0.20O2−x, an in situ high temperature x-ray diffraction study

Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up

Lattice parameter changes associated with the rim-structure formation in high burn-up UO2 fuels by micro x-ray diffraction

In situ high temperature X-ray diffraction study of UO2 nanoparticles

Laser melting of nano-crystalline uranium dioxide

Stereological evolution of the rim structure in PWR-fuels at prolonged irradiation: Dependencies with burn-up and temperature

Lattice contraction in the rim zone as controlled by recrystallization: Additional evidence

Room-temperature microindentation behaviour of LWR-fuels, part 1: fuel microhardness

Formation of the rim structure in high burnup fuel

Comments on the threshold porosity for fission gas release in high burn-up fuels

Fabrication and characterization of (U, Am)O 2− x transmutation targets

Fission gas release from UO^sub 2^ nuclear fuel: A review

Phase characterisation of simulated high burn-up UO2 fuel

Bulk and Young's modulus of doped UO2 by synchrotron diffraction under high pressure and Knoop indentation

High burn-up rim structure: evidences that xenon-depletion, pore formation and grain subdivision start at different local burn-ups

Nanocrystalline ZrO2 ceramics with idealized macropores

Fabrication and characterization of (U, Am)O2-x transmutatio

Fractal analysis of high burn-up structures in UO2

In situ high temperature X-ray diffraction study of U[O.sub.2] nanoparticles

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