Fresh Fuel Characterization of U-Mo Alloys (original) (raw)

Update on Fresh Fuel Characterization of U-Mo Alloys

Ramprashad Prabhakaran

2009

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

Sibasis Chakraborty, G. Choudhuri, Subhrajyoti Chakraborty

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Fuel clad chemical interaction of U-Mo fast reactor fuel

Sibasis Chakraborty

Journal of Nuclear Materials, 2019

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IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL

Emmanuel Perez

Nuclear Engineering and Technology, 2014

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

Thomas Wiencek

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In situ TEM and synchrotron characterization of U–10Mo thin specimen annealed at the fast reactor temperature regime

walid mohamed

Materials Characterization, 2015

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Stability of γ-UMo Nuclear Fuel Alloys by Thermal Analysis

Delvonei De Andrade

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

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FY16 Status Report for the Uranium-Molybdenum Fuel Concept

Ryan Webster

2016

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

Jian Gan

JOM, 2017

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

Thomas Wiencek

1987

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XRD and SEM/EDS characterization of two quaternary fuel alloys (U-2.5Mo-2.5Ti-5.0Zr and U-1.5Mo-1.5Ti-7.0Zr in wt. %) for fast reactors

Jinsuo Zhang

Materials Characterization, 2020

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U-Si and U-Si-Al dispersion fuel alloy development for research and test reactors

Thomas Wiencek

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Effect of homogenization and hot rolling on the mechanical properties, microstructure and corrosion behavior of U–10Mo monolithic fuel

Ramprashad Prabhakaran

Journal of Nuclear Materials, 2019

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

Jian Gan

Scripta Materialia, 2016

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Elevated temperature microcantilever testing of fresh U-10Mo fuel

Daniel Jädernäs

Journal of Nuclear Materials, 2019

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

GJ Prasad

Journal of Alloys and Compounds, 2009

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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

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Session 2 Fuel development, qualification, fabrication and licensing

G. Hofman

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

shenyang Hu

2021

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Non-Destructive Characterization of UO2+x Nuclear Fuels

Kenneth McClellan

Microscopy Today, 2017

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

Thomas Wiencek

1987

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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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Small-scale Specimen Testing of Monolithic U-Mo Fuel Foils

Ramprashad Prabhakaran

Proceedings of the 30th …, 2008

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Fuel Swelling and Creep Analysis for a MURR LEU U-10Mo Monolithic Plate

Walid Mohamed

2019

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U-Si and U-Si-Ai Dispersion Fuel Alloy Development for Research and Test Reactors

Thomas Wiencek

Nuclear Technology, 1983

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Low-enriched uranium-molybdenum fuel plate development

Thomas Wiencek

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Phase characteristics of a number of U–Pu–Am–Np–Zr metallic alloys for use as fast reactor fuels

Dennis Keiser

Journal of Nuclear Materials, 2010

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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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Fuel Thermo-physical Characterization Project: Fiscal Year 2014 Final Report

Edgar Buck

2015

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CLADDING SURVEY FOR THE ENRICO FERMI REACTOR U-15 Wt.% Mo BASE DISPERSION- TYPE FUEL ELEMENT

Manuel Alamo Martin

1960

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Preliminary Investigation of the Use of Monolithic U-Mo Fuel in the Mit Reactor

Edward Pilat

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

W. Petry

Journal of Nuclear Materials, 2009

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

W. Petry

Journal of Nuclear Materials, 2014

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Gamma Uranium Molybdenum Alloy: Its Hydride and Performance

Hichame Asrary

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