Fracture of Zircaloy-4 Fuel Cladding Tubes with Hydride Blisters (original) (raw)
Fracture of Zircaloy-4 cladding tubes with or without hydride blisters in uniaxial to plane strain conditions with standard and optimized expansion due to compression tests
Quentin Auzoux, Jérôme Crépin
Materials Science and Engineering: A, 2014
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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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An evaluation of hydrided Zircaloy-4 cladding fracture behavior by X-specimen test
Hsiao-Hung Hsu
Journal of Alloys and Compounds, 2006
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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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Simulating hydride embrittlement on cold-worked stress-relieved Zircaloy-4 with Gurson-Tvergaard-Needleman damage mode
Jean Des
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An elasto-plastic fracture mechanics based model for assessment of hydride embrittlement in zircaloy cladding tubes
Vratko Vokal
Journal of Nuclear Materials, 2010
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ScienceDirect Effects of hydride on crack propagation in zircaloy-4
Sunaina Dixit
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The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding—An International Atomic Energy Agency Coordinated Research Program
Виктор Иноземцев
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Rupture of spent fuel Zircaloy cladding in dry storage due to delayed hydride cracking
Keith Yang
Nuclear Engineering and Design, 2008
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Behavior and rupture of hydrided ZIRCALOY-4 tubes and sheets
E. Andrieu
Metallurgical and Materials Transactions A, 1998
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Fracture of Zr-alloy pressure tubes due to hydride blister formation
Leslie Banks-sills
2006
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Characterization of Axial Cracking Morphology of Zircaloy Cladding Tubes
Gopal Sanyal
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Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes
Quentin Auzoux
Journal of Nuclear Materials, 2014
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The effect of strain biaxiality on the fracture of zirconium alloy fuel cladding
Jacques Besson
Journal of Nuclear Materials, 2021
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Effect of radial hydrides on the axial and hoop mechanical properties of Zircaloy-4 cladding
Carol Chu
Journal of Nuclear Materials, 2007
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Evaluation of fracture toughness of Zr-2.5 Nb pressure tube alloy as a function of hydrogen content, deformation rate and temperature
arvind bind
2011
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Failure of hydrided zircaloy-4 fuel cladding tubes under RIA loading conditions
Xavier Averty
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Investigation of elevated-temperature mechanical properties of d- hydride precipitate in Zircaloy-4 fuel cladding tubes using nanoindentation
Sunaina Dixit
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Investigation of failure behavior of two different types of Zircaloy clad tubes used as nuclear reactor fuel pins
Gopal Sanyal
Engineering Failure Analysis, 2011
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Evaluation of effect of hydrogen on toughness of Zircaloy-2 by instrumented drop weight impact testing
raj singh
Journal of Nuclear Materials, 2006
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3960 - Effects of the Hydride Concentration and the Near Crack Tip Gradient on the Fracture Toughness of ZIRCALOY-4
Graciela Bertolino
Icf11 Italy 2005, 2013
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Temperature increase of Zircaloy-4 cladding tubes due to plastic heat dissipation during tensile tests at 0.1–10s−1 strain rates
Jérôme Crépin, Quentin Auzoux
Journal of Nuclear Materials, 2014
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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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Effect of direction of approach of test temperature on fracture toughness of Zr–2.5Nb pressure tube material
arvind bind
Materials Science and Engineering: A, 2015
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Influence of hydrogen content on fracture toughness of CWSR Zr–2.5Nb pressure tube alloy
arvind bind
Journal of Nuclear Materials, 2013
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High-pressure hydriding of Zircaloy cladding by the thermogravimetry and tube-burst techniques
Lars Hallstadius
Journal of Nuclear Materials, 2005
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Influence of the crack-tip hydride concentration on the fracture toughness of Zircaloy-4
Graciela Bertolino
Journal of Nuclear Materials, 2006
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Hydrides Effect on the SCC Initiation on Zircaloy4 Claddings
Alice Dinu
Advanced Materials Research, 2007
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Behavior of zirconium fuel cladding under fast pressurization rates
Jun Kim
Nuclear Engineering and Design, 2008
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Effects of Zr-hydride distribution of irradiated Zircaloy-2 cladding in RIA-simulating pellet-clad mechanical interaction testing
David Schrire
Nuclear Engineering and Technology, 2018
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