original ) (raw )Analysis of the absorbed hydrogen in cladding tubes applied in the QUENCH-LOCA tests
Juri Stuckert
2012
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Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations
Sunaina Dixit
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Quantification and local distribution of hydrogen within Zircaloy-4 PWR nuclear fuel cladding tubes at the nuclear microprobe of the Pierre Süe Laboratory from μ-ERDA
Jean-Christophe Brachet
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2008
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Delayed Hydride Cracking in Zircaloy Fuel Cladding - an Iaea Coordinated Research Programme
Виктор Иноземцев
Nuclear Engineering and Technology
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The combined influence of hydrogen and oxidation on fuel cladding mechanical behaviour during simulated normal operations
Jean Des
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Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
Sunaina Dixit
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Failure of hydrided zircaloy-4 fuel cladding tubes under RIA loading conditions
Jacques Besson
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Neutron Imaging Investigations of the Secondary Hydriding of Nuclear Fuel Cladding Alloys during Loss of Coolant Accidents
Juri Stuckert
Physics Procedia, 2015
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Severe Fuel Damage Experiments With Advanced Cladding Materials to be Performed in the QUENCH Facility (QUENCH-ACM)
Juri Stuckert
Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 2008
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Behavior and failure of uniformly hydrided Zircaloy-4 fuel claddings between 25°C and 480°C under various stress states, including RIA loading conditions
Xavier Averty
Engineering Failure Analysis, 2010
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Results of Severe Fuel Damage Experiment QUENCH-14 with Advanced Rod Cladding M5®. (KIT Scientific Reports ; 7549)
Juri Stuckert
2010
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Modeling the water side corrosion and hydrogen pickup of VVER 1000 fuel clad
masoud mansouri
Nuclear Technology and Radiation Protection, 2018
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Modeling hydrogen localization in Zircaloy cladding subjected to temperature gradients
Katheren Rayssa Bosson Nantes
Journal of Nuclear Materials, 2024
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Corrosion and Hydrogen Uptake in Zirconium Claddings Irradiated in Light Water Reactors
Mirco Große
Zirconium in the Nuclear Industry: 17th Volume, 2014
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Hydride fuel behavior in LWRs
Marowen Ng
Journal of Nuclear Materials, 2005
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High Temperature Steam Corrosion of Cladding for Nuclear Applications: Experimental
Michael V Glazoff , Shannon Bragg-Sitton
Ceramic Engineering and Science Proceedings, 2013
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Effects of hydrogen on thermal creep behaviour of Zircaloy fuel cladding
Sunaina Dixit
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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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A model for uniform Zircaloy clad corrosion in pressurized water reactors
A. R. Massih
Nuclear Engineering and Design, 1995
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A REVIEW OF FAILURE MODES OF NUCLEAR FUEL CLADDING A Review of Failure Modes of Nuclear Fuel Cladding
Abdoulhadi A . Borhana Omran
Journal of Engineering Science and Technology, 2019
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Behavior of zirconium fuel cladding under fast pressurization rates
Jun Kim
Nuclear Engineering and Design, 2008
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Uranium–zirconium hydride fuel properties
Bojan Petrovic
Nuclear Engineering and Design, 2009
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Hydrogen in zirconium alloys: A review
mahmut cinbiz
Journal of Nuclear Materials, 2019
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LWRS Fuels Pathway: Engineering Design and Fuels Pathway Initial Testing of the Hot Water Corrosion System
John Garnier
2012
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Icone 17-75099 Analysis of the QUENCH-14 Bundle Test with M 5 ® Cladding
jonathan birchley
2009
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Zirconium Alloys for Fuel Element Structures
Gerhard Bart
CHIMIA, 2005
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Influence of the Cooling Scenario on the Post-Quench Mechanical Properties of Pre-Hydrided Zircaloy-4 Fuel Claddings after high Temperature Steam Oxidation (LOCA Conditions)
Valérie Vandenberghe , Jean-Christophe Brachet
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Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes
Richárd Nagy
Nuclear Engineering and Technology, 2021
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Dynamic finite element analysis of segmented mandrel tests of hydrogenated E110 fuel cladding tubes
Richárd Nagy
Materials Today Communications, 2020
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