High-energy synchrotron study of in-pile-irradiated U–Mo fuels (original) (raw)

TEM and XAS investigation of fission gas behaviors in U-Mo alloy fuels through ion beam irradiation

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Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2Fuels

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Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2009

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High Burn-up Structure in Nuclear Fuel: Impact on Fuel Behavior

J. Lamontagne

EPJ Web of Conferences, 2016

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Observed Changes in As-Fabricated U-10Mo Monolithic Fuel Microstructures After Irradiation in the Advanced Test Reactor

Jian Gan

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Microstructural-Level Fuel Performance Modeling of U-Mo Monolithic Fuel

shenyang Hu

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Heavy ion irradiation of U–Mo/Al dispersion fuel

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2006

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Thermal properties of U–Mo alloys irradiated to moderate burnup and power

Andrew Casella

Journal of Nuclear Materials, 2015

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Heterogeneous UO2 fuel irradiated up to a high burn-up: Investigation of the HBS and of fission product releases

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Nano-Scale Fission Product Phases in an Irradiated U-7Mo Alloy Nuclear Fuel

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Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix

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STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3

Anditania Sari Dwi Putri

Urania (Tangerang), 2022

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Microstructural characterization of Irradiated U-Pu-Zr Fuels

Thaddeus Rahn

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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

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Update on Fresh Fuel Characterization of U-Mo Alloys

Ramprashad Prabhakaran

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Nuclear Energy Enabling Technology Enhanced Generic Phase-field Model of Irradiation Materials: Fission Gas Bubble Growth Kinetics in Polycrystalline UO 2

Robert Montgomery

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Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System

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Journal of Nuclear Materials, 2021

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A Monte Carlo model of irradiation-induced recrystallization in polycrystalline UMo fuels

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The high burn-up structure in nuclear fuel

Thierry Wiss

Materials Today, 2010

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Fresh Fuel Characterization of U-Mo Alloys

Jian Gan

2008

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The development of a mechanistic code on fission product behavior in the polycrystalline UO2 fuel

Vladimir Likhanskii

Nuclear Engineering and Design, 2000

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Prototypic irradiation testing of high-density U-Mo alloy dispersion fuels

Thomas Wiencek

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Non-Destructive Characterization of UO2+x Nuclear Fuels

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Potential annealing treatments for tailoring the starting microstructure of low-enriched U–Mo dispersion fuels to optimize performance during irradiation

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Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide

Lingfeng He

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Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo

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The Effect of Re-Solution Models on Fission Gas Disposition in Irradiated UO2 Fuel

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Enhanced Generic Phase-field Model of Irradiation Materials: Fission Gas Bubble Growth Kinetics in Polycrystalline UO2

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