original ) (raw )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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Analysis of the absorbed hydrogen in cladding tubes applied in the QUENCH-LOCA tests
Juri Stuckert
2012
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Investigation of the 3D hydrogen distribution in zirconium alloys by means of neutron tomography
Pavel Trtik
International Journal of Materials Research, 2020
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Characterization of crud deposited on fuel rods under HWC environment in Kuosheng Nuclear Power Plant
翠玲 蔡
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Experimental Research Concerning Waterside Corrosion of Fuel Cladding in Candu Reactor
Dumitra Lucan
Journal of Science and Arts, 2024
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Special Issue: Behavior of Materials (Alloys, Coatings) in Conditions Specific to Gen IV Nuclear Reactors
Manuela Fulger
Coatings
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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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Hydrogen diffusion and precipitation in duplex zirconium nuclear fuel cladding quantified by high-resolution neutron imaging
Mirco Große
Journal of Nuclear Materials, 2019
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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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Non-destructive Evaluation of Irradiated Nuclear Fuels and Structural Components from Indian Reactors
Nitin Kumawat
2017
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Application of neutron radiography to study material processes during hypothetical severe accidents in nuclear reactors
Juri Stuckert
Journal of Materials Science, 2011
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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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Oxidation of Zircaloy Fuel Cladding in Water-Cooled Nuclear Reactors
Digby Macdonald
2006
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Modelling of Nuclear Fuel Cladding Tubes Corrosion
Martin Ševeček
Acta Polytechnica CTU Proceedings, 2016
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Roles of Radiolytic and Externally Generated H2 in the Corrosion of Fractured Spent Nuclear Fuel
David Shoesmith
Environmental science & technology, 2016
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Corrosion Behavior of Zirconium Alloy Nuclear Fuel Cladding
Anna C. Fraker
MRS Proceedings, 1989
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Corrosion Monitoring in Nuclear Systems
Jorge Uruchurtu
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In-situ neutron radiography investigations of hydrogen diffusion and absorption in zirconium alloys
E Lehmann
Nuclear Instruments & Methods in Physics Research Section a-Accelerators Spectrometers Detectors and Associated Equipment, 2011
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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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Investigation of hydrogen diffusivity in Zr-2.5%Nb alloy pressure tube material using Metallography and Neutron Radiography
mayank shukla
Journal of Nuclear Materials, 2021
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Development of new reactor fuel materials: hydrogenation properties of UThZr alloys and neutron irradiation effects on their hydrides
Hadi Suwarno
Journal of Nuclear Materials, 1997
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Determination of very low concentrations of hydrogen in zirconium alloys by neutron imaging
Mirco Große
Journal of Nuclear Materials, 2018
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Specific Aspects of Internal Corrosion of Nuclear Clad Made of Zircaloy
Tony Montesin
DDF, 2012
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Assessment at Cea of Coated Nuclear Fuel Cladding for LWRS with Increased Margins in Loca and Beyond Loca Conditions
Marc Tupin
2013
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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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Assessment at CEA of coated nuclear fuel cladding for LWRs with increasing margins in LOCA and beyond LOCA conditions
Jean-Christophe Brachet , Valérie Vandenberghe
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NUCLEAR FUEL CLADDING: Review of the Zircaloy cladding and basic analysis of the model with the single hydride
Vasile Radu
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Revisiting Stainless Steel as PWR Fuel Rod Cladding after Fukushima Daiichi Accident
Daniel de Souza Gomes
Journal of Energy and Power Engineering, 2014
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