Symposium T – Materials Innovations for Next-Generation Nuclear Energy
Research Article
Modeling and Simulation of Thermophysical Properties of Minor Actinides-Containing Oxide Fuels
- Published online by Cambridge University Press: 01 February 2011, 1043-T09-06
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Indentation study of titanium, zirconium, and hafnium hydrides
- Published online by Cambridge University Press: 01 February 2011, 1043-T09-11
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Preparation of Nitride Fuel by Spark Plasma Sintering Technique
- Published online by Cambridge University Press: 01 February 2011, 1043-T13-04
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Microstuctural Characterization of the Radiation Effects in ZrC, a Potential Material for Next Generation Nuclear Plants
- Published online by Cambridge University Press: 01 February 2011, 1043-T02-01
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Oxidation Behavior of Zr-Nb Alloys at 973-1273 K in Air
- Published online by Cambridge University Press: 01 February 2011, 1043-T09-01
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On Modeling the Evolution of Radiation Damage in Silicon Carbide
- Published online by Cambridge University Press: 01 February 2011, 1043-T02-05
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Thermal Properties of Simulated High Burn up Nitride Fuels and Nitride ADS Targets
- Published online by Cambridge University Press: 01 February 2011, 1043-T13-03
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Characterization of Point Defect Generation, Migration and Coalescence in Irradiated SiC by Atomistic Simulation
- Published online by Cambridge University Press: 01 February 2011, 1043-T02-04
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Existence of a critical temperature for corrosion of alloy 617 in He-CO-CO2 environment
- Published online by Cambridge University Press: 01 February 2011, 1043-T01-03
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Characteristics of Radiation-induced Defects in Fluorite Structure Oxides Formed by Electron Irradiation
- Published online by Cambridge University Press: 01 February 2011, 1043-T12-02
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Effects of Hydrogen Absorption on the Mechanical Properties of Zr-Nb Alloys
- Published online by Cambridge University Press: 01 February 2011, 1043-T09-08
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In-situ Formation of Bismuth-Based Iodine Waste Forms
- Published online by Cambridge University Press: 01 February 2011, 1043-T12-05
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Insights into Radiation Tolerance of Ceramics from Large Scale Molecular Dynamics Simulations
- Published online by Cambridge University Press: 01 February 2011, 1043-T06-03-E06-03
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SiC, TiC and ZrC Nanostructured Ceramics: Elaboration and Potentialities for Nuclear Applications
- Published online by Cambridge University Press: 01 February 2011, 1043-T02-02
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Study on Effects of Heavy Ion Irradiation on CeO2 by Using Synchrotron Radiation X-Ray Absorption Spectroscopy -as a Simulation Study for Radiation Damage in High-Burnup Light Water Reactor Fuels-
- Published online by Cambridge University Press: 01 February 2011, 1043-T09-02
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Progress in Out-Of-Pile Study of Low Enriched UMo/AlSi Fuel
- Published online by Cambridge University Press: 01 February 2011, 1043-T09-10
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Light Water Reactor Fuel Degradation Mechanisms at High Burnup: Implications to Generation IV Materials
- Published online by Cambridge University Press: 01 February 2011, 1043-T10-02
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Influence of Phase Stability on Radiation Damage Properties: Plutonium-Gallium Alloys
- Published online by Cambridge University Press: 01 February 2011, 1043-T04-03
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Thermodynamic Modeling of Plutonium Oxide Containing Americium
- Published online by Cambridge University Press: 01 February 2011, 1043-T09-05
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Study of Fission and High-burnup Induced Restructuring of Nuclear Fuel Ceramics - Applying Computer Science to Investigate Kinetic Process
- Published online by Cambridge University Press: 01 February 2011, 1043-T12-04
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