Zirconium Alloys for Fuel Element Structures
Gerhard Bart
CHIMIA, 2005
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Behavior of unirradiated Zr based uranium metal fuel under reactivity initiated accident conditions
Mikhail Baryshnikov
Nuclear Engineering and Design, 2008
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Microstructural investigation of irradiation damage behavior of proton irradiated Zr-1 wt.% Nb fuel cladding alloy
aruna devi
Journal of Nuclear Materials, 2019
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Low-Burnup Irradiation Behavior of Fast Reactor Metal Fuels Containing Minor Actinides
Bruno Fontaine
Nuclear Technology, 2009
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The PROMETRA program: a reliable material database for highly irradiated Zircaloy-4, ZirloTM and M5TM fuel claddings
Jean Des, P. Yvon, Xavier Averty
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EFFECT OF CHROMIUM COATINGS ON THE MECHANICAL PROPERTIES OF Zr1Nb FUEL CLADDINGS IN LONGITUDINAL AND TRANSVERSE DIRECTIONS
Yevgeniy Krainyuk
Problems of Atomic Science and Technology, 2019
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Prototypic irradiation testing of high-density U-Mo alloy dispersion fuels
Thomas Wiencek
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Engineering & Microstructure Scale PIE Report on EBR-II X441A Metallic Fuel Pins for the MORPH Experiment
Thaddeus Rahn
2022
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Development of Eutectic Free Cladding Materials for Metallic Fuel
Moriyasu Tokiwai
Journal of Nuclear Science and Technology
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Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding
Jinsuo Zhang
Nuclear Science and Engineering, 2020
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Microstructural characterization of U-Zr alloy fuel slugs for sodium-cooled fast reactor
Se Ahn Song
Surface and Interface Analysis, 2012
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Advanced Fabrication Technique and Thermal Performance Prediction of U-Mo/Zr-alloy Dispersion Fuel Pin for High Burnup PWR
su wardi
Telematika, 2011
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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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Post irradiation examination of a uranium-zirconium hydride TRIGA fuel element
Eric Woolstenhulme
Frontiers in Energy Research
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CEA studies on High temperature oxidation and hydriding of Zr based nuclear fuel claddings upon LOCA transients phenomenology, mechanisms and modelling => consequences on mechanical properties
C. Toffolon-masclet
2016
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Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding
gene stein
Journal of Nuclear Materials, 2017
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Preparation, analysis and irradiation of hydrided U–Th–Zr alloy samples for a new fuel
Hadi Suwarno
Journal of Alloys and Compounds, 1998
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Understanding Corrosion and Hydrogen Pickup of Zirconium Fuel Cladding Alloys: The Role of Oxide Microstructure, Porosity, Suboxides, and Second-Phase Particles
C. Grovenor
Zirconium in the Nuclear Industry: 18th International Symposium, 2018
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Metallic Fuel element Materials, Comprehensive Technical Report, General Electric Direct-Air-Cycle, Aircraft Nuclear Propulsion Program
Rock Level
1962
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Performance evaluation and post-irradiation examination of a novel LWR fuel composed of U0.17ZrH1.6 fuel pellets bonded to Zircaloy-2 cladding by lead bismuth eutectic
Edgar Buck
Journal of Nuclear Materials, 2016
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Formation of Pellet-Cladding Bonding Layer in High Burnup BWR Fuels
katsumi une
Journal of Nuclear Science and Technology, 1997
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A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions
Jacques Besson
Journal of Nuclear Materials, 2008
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THE FRACTURE AND SPALLATION OF ZIRCONIA LAYERS IN HIGH BURNUP PWR FUEL CLADDINGS SUBMITTED TO RIA TRANSIENTS
Jean Des
Proceedings of 18th …, 2005
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Modeling of Gap Closure in Uranium-Zirconium Alloy Metal Fuel - A Test Problem
John Turner
2009
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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
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Corrosion Behavior of Zirconium Alloy Nuclear Fuel Cladding
Anna C. Fraker
MRS Proceedings, 1989
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The Effect of Air Fraction in Steam on the Embrittlement of Zry-4 Fuel Cladding Oxidized at 1273–1573 K
Martin Negyesi
Oxidation of Metals, 2019
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Microstructural characterization of Irradiated U-Pu-Zr Fuels
Thaddeus Rahn
Microscopy and Microanalysis
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Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe
Walid Mohamed Rashad Mohamed
Journal of Nuclear Materials, 2015
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Microstructural Characterization of the U-9.1Mo Fuel/AA6061 Cladding Interface in Friction-Bonded Monolithic Fuel Plates Irradiated in the RERTR-6 Experiment
Jian Gan
Metallurgical and Materials Transactions E, 2015
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Incorporation of Integral Fuel Burnable Absorbers Boron and Gadolinium into Zirconium-Alloy Fuel Clad Material
Edward Lahoda
2004
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TEM and XAS investigation of fission gas behaviors in U-Mo alloy fuels through ion beam irradiation
Walid Mohamed
Journal of Nuclear Materials, 2017
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Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings
Bright Afornu
Coatings
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Nano-Scale Fission Product Phases in an Irradiated U-7Mo Alloy Nuclear Fuel
Jian Gan
Microscopy Today, 2014
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