Uranium–molybdenum nuclear fuel plates behaviour under heavy ion irradiation: An X-ray diffraction analysis (original) (raw)

Annealing tests of in-pile irradiated oxide coated U–Mo/Al–Si dispersed nuclear fuel

W. Petry

Journal of Nuclear Materials, 2014

Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

Walid Mohamed Rashad Mohamed

Journal of Nuclear Materials, 2015

Irradiation effects and micro-structural changes in large grain uranium dioxide fuel investigated by micro-beam X-ray diffraction

Daniel Grolimund

Journal of Nuclear Materials, 2014

High-energy synchrotron study of in-pile-irradiated U–Mo fuels

Scripta Materialia, 2016

IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL

Emmanuel Perez

Nuclear Engineering and Technology, 2014

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

W. Petry

Journal of Nuclear Materials, 2011

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

Dennis Keiser

Journal of Nuclear Materials, 2011

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

Walid Mohamed

Journal of Nuclear Materials, 2017

UMo/Al nuclear fuel quantitative analysis via high energy X-ray diffraction

Juan Rodríguez-Carvajal

2011

Low-enriched uranium-molybdenum fuel plate development

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

Stability of γ-UMo Nuclear Fuel Alloys by Thermal Analysis

Delvonei De Andrade

Current Research in Nuclear Reactor Technology in Brazil and Worldwide, 2013

Fuel clad chemical interaction of U-Mo fast reactor fuel

Sibasis Chakraborty

Journal of Nuclear Materials, 2019

Neutron Irradiation of U3Si5 and Al43Mo4U6 Compounds. First Results

Rubén González

Procedia Materials Science, 2015

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

JOM, 2017

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

Roberto Caciuffo

Journal of Solid State Chemistry, 2013

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

Microscopy Today, 2014

Micro-structural study and Rietveld analysis of fast reactor fuels:U-Mo fuels

Sibasis Chakraborty, G. Choudhuri, Subhrajyoti Chakraborty

Stress Analysis in UMo-Al Fuel Using X-Ray Diffraction

Regis Kubler

Materials Science Forum, 2011

Non-Destructive Characterization of UO2+x Nuclear Fuels

Kenneth McClellan

Microscopy Today, 2017

The use of U/sub 3/Si/sub 2/ dispersed in aluminum in plate-type fuel elements for research and test reactors

1987

Microstructural characterization of Irradiated U-Pu-Zr Fuels

Thaddeus Rahn

Microscopy and Microanalysis

FY16 Status Report for the Uranium-Molybdenum Fuel Concept

Ryan Webster

2016

Progress in understanding fission-product behaviour in coated uranium-dioxide fuel particles

Marc Barrachin

Journal of Nuclear Materials, 2009

Application of ion beams in materials science of radioactive waste forms: focus on the performance of spent nuclear fuel

Lech Nowicki

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2005

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

J. Lamontagne

Journal of Nuclear Materials, 2013

Tem Characterization of Irradiated U3SI2/AL Dispersion Fuel

2010

Development, preparation and characterization of uranium molybdenum alloys for dispersion fuel application

GJ Prasad

Journal of Alloys and Compounds, 2009

Unirradiated characteristics of U-Si alloys as dispersed-phase fuels

1987

Ion implantation studies of UO2 and UN

Andrzej Turos

Journal of Nuclear Materials, 1992

Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels

abhishek mehta

Journal of Nuclear Materials, 2017

Post irradiation examination of a uranium-zirconium hydride TRIGA fuel element

Eric Woolstenhulme

Frontiers in Energy Research

Structural modifications in uranium dioxide irradiated with swift heavy ions

Jean-Claude Dran

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 1997

Alpha self-irradiation effect on the local structure of the U0.85Am0.15O2±x solid solution

Thierry Delahaye

Journal of Solid State Chemistry, 2012