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Raman spectroscopic investigation of graphitization of diamond during spark plasma sintering of UO2-diamond composite nuclear fuel

Journal of nuclear materials, 2016-07, Vol.475 (C), p.1-5

2016

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Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS)

Journal of nuclear materials, 2013-04, Vol.435 (1-3), p.1-9

2013

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Influence of processing parameters on thermal conductivity of uranium dioxide pellets prepared by spark plasma sintering

Journal of the European Ceramic Society, 2014-07, Vol.34 (7), p.1791-1801

2014

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Energetics of intrinsic point defects in uranium dioxide from electronic-structure calculations

Journal of nuclear materials, 2009-01, Vol.384 (1), p.61-69

2009

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Radiation dose rate distributions of spent fuel dry casks estimated with MAVRIC based on detailed geometry and continuous-energy models

Annals of nuclear energy, 2018-07, Vol.117 (C), p.84-97

2018

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Master sintering curves for UO2 and UO2–SiC composite processed by spark plasma sintering

Journal of nuclear materials, 2014-11, Vol.454 (1-3), p.427-433

2014

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Thermal transport properties of uranium dioxide by molecular dynamics simulations

Journal of nuclear materials, 2008-04, Vol.375 (3), p.388-396

2008

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Mechanical properties and XRD studies of silicon carbide inert matrix fuel fabricated by a low temperature polymer precursor route

Journal of nuclear materials, 2013-01, Vol.432 (1-3), p.152-159

2013

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Thermal Transport in Off-Stoichiometric Uranium Dioxide by Atomic Level Simulation

Journal of the American Ceramic Society, 2009-04, Vol.92 (4), p.850-856

2009

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Low-temperature synthesis of silicon carbide inert matrix fuel through a polymer precursor route

Journal of nuclear materials, 2011-02, Vol.409 (3), p.199-206

2011

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Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation

JOM (1989), 2011-08, Vol.63 (8), p.73-79

2011

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Synthesis and pyrolysis of novel polysilazane to SiBCN ceramic

Journal of non-crystalline solids, 2005-10, Vol.351 (37), p.2995-3005

2005

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Spark plasma sintering of diamond-reinforced uranium dioxide composite fuel pellets

Nuclear engineering and design, 2015-12, Vol.294 (C), p.52-59

2015

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Development and Testing of a Nanotech Nuclear Battery for Powering MEMS Devices

Nuclear technology, 2011-04, Vol.174 (1), p.119-123

2011

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The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2–SiC composites

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.245-252

2013

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Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage

Annals of nuclear energy, 2020-06, Vol.140 (C), p.107145, Article 107145

2020

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Exploration of Viability of Spark Plasma Sintering for Commercial Fabrication of Nuclear Fuel Pellets

Nuclear technology, 2017-11, Vol.200 (2), p.144-158

2017

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Enhanced Thermal Conductivity for LWR Fuel

Nuclear technology, 2010-01, Vol.169 (1), p.61-72

2010

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Influence of Carbon Nanotube Dispersion in UO2-Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering

Nuclear technology, 2015-03, Vol.189 (3), p.258-267

2015

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Toward an Atomistically Informed Fuel Performance Code: Thermal Properties Using FRAPCON and Molecular Dynamics Simulation

Nuclear technology, 2009-03, Vol.165 (3), p.308-312

2009

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Master sintering curves for UO sub(2) and UO sub(2)-SiC composite processed by spark plasma sintering

Journal of nuclear materials, 2014-11, Vol.454 (1-3), p.427-433

2014

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Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage

Annals of nuclear energy, 2019-10, Vol.140

2019

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INFLUENCE OF CARBON NANOTUBE DISPERSION IN UO sub(2)-CARBON NANOTUBE CERAMIC MATRIX COMPOSITES UTILIZING SPARK PLASMA SINTERING

Nuclear technology, 2015-03, Vol.189 (3), p.258-267

2015

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Influence of Carbon Nanotube Dispersion in UO 2 –Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering

Nuclear technology, 2015-03, Vol.189 (3), p.258-267

2015

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The effects of oxygen, carbon dioxide and water vapor on reprocessing silicon carbide inert matrix fuels by corrosion in molten potassium carbonate

Journal of nuclear materials, 2011-04, Vol.411 (1), p.126-130

2011

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Raman spectroscopic investigation of graphitization of diamond during spark plasma sintering of UO2-diamond composite nuclear fuel

Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS)

Influence of processing parameters on thermal conductivity of uranium dioxide pellets prepared by spark plasma sintering

Energetics of intrinsic point defects in uranium dioxide from electronic-structure calculations

Radiation dose rate distributions of spent fuel dry casks estimated with MAVRIC based on detailed geometry and continuous-energy models

Master sintering curves for UO2 and UO2–SiC composite processed by spark plasma sintering

Thermal transport properties of uranium dioxide by molecular dynamics simulations

Mechanical properties and XRD studies of silicon carbide inert matrix fuel fabricated by a low temperature polymer precursor route

Thermal Transport in Off-Stoichiometric Uranium Dioxide by Atomic Level Simulation

Low-temperature synthesis of silicon carbide inert matrix fuel through a polymer precursor route

Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation

Synthesis and pyrolysis of novel polysilazane to SiBCN ceramic

Spark plasma sintering of diamond-reinforced uranium dioxide composite fuel pellets

Development and Testing of a Nanotech Nuclear Battery for Powering MEMS Devices

The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2–SiC composites

Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage

Exploration of Viability of Spark Plasma Sintering for Commercial Fabrication of Nuclear Fuel Pellets

Enhanced Thermal Conductivity for LWR Fuel

Influence of Carbon Nanotube Dispersion in UO2-Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering

Toward an Atomistically Informed Fuel Performance Code: Thermal Properties Using FRAPCON and Molecular Dynamics Simulation

Master sintering curves for UO sub(2) and UO sub(2)-SiC composite processed by spark plasma sintering

Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage

INFLUENCE OF CARBON NANOTUBE DISPERSION IN UO sub(2)-CARBON NANOTUBE CERAMIC MATRIX COMPOSITES UTILIZING SPARK PLASMA SINTERING

Influence of Carbon Nanotube Dispersion in UO 2 –Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering

The effects of oxygen, carbon dioxide and water vapor on reprocessing silicon carbide inert matrix fuels by corrosion in molten potassium carbonate

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