Influence of Hydrogen Content on the ?/? Phase Transformation Temperatures and on the Thermal-Mechanical Behavior of Zy-4, M4 (ZrSnFeV), and M5? (ZrNbO) Alloys During the First Phase of LOCA Transient, Zirconium in the Nuclear Industry: Thirteenth International Symposium, p.673-673-29 ,
, Influence of hydrogen content on the ?/? phase transformation temperatures and on the thermal-mechanical behavior of Zy-4, M4 (ZrSnFeV), and M5? (ZrNbO) alloys during the first phase of LOCA transient, Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423, pp.673-701, 2002.
Development of an Oxygen Embrittlement Criterion for Zircaloy Cladding Applicable to Loss-of-Coolant Accident Conditions in Light-Water Reactors, Zirconium in the Nuclear Industry, p.600-600-28 ,
Failure-Bearing Capability of Oxidized Zircaloy-4 Cladding under Simulated Loss-of-Coolant Condition, Journal of Nuclear Science and Technology, vol.20, issue.11, pp.941-950, 1983. ,
Cladding embrittlement during postulated loss-of-coolant accidents., 2008. ,
Behavior of High Burn-up Fuel Cladding under LOCA Conditions, Journal of Nuclear Science and Technology, vol.46, issue.7, pp.763-769, 2009. ,
QUENCH-LOCA program at KIT on secondary hydriding and results of the commissioning bundle test QUENCH-L0, Nuclear Engineering and Design, vol.255, pp.185-201, 2013. ,
Contribution to the understanding of brittle fracture conditions of zirconium alloy fuel cladding tubes during LOCA transient, Journal of Nuclear Materials, vol.527, p.151815, 2019. ,
URL : https://hal.archives-ouvertes.fr/hal-02455379
Development of an Oxygen Embrittlement Criterion for Zircaloy Cladding Applicable to Loss-of-Coolant Accident Conditions in Light-Water Reactors, Zirconium in the Nuclear Industry, p.600-600-28 ,
?Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe, Journal of Nuclear Materials, vol.488, pp.267-286, 2017. ,
Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions, Zirconium in the Nuclear Industry: 15th International Symposium, p.91-91-28 ,
Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5? Alloys in LOCA Conditions, Journal of ASTM International, vol.5, 2008. ,
Transformation characteristics of rapidly heated and quenched zircaloy-4-oxygen alloys, Journal of Nuclear Materials, vol.79, issue.1, pp.83-94, 1979. ,
Creep flow and fracture behavior of the oxygen-enriched alpha phase in zirconium alloys, Scripta Materialia, vol.117, pp.20-23, 2016. ,
URL : https://hal.archives-ouvertes.fr/hal-01288691
Mechanical Behavior at High Temperatures of Highly Oxygen- or Hydrogen-Enriched ? and Prior-? Phases of Zirconium Alloys, Zirconium in the Nuclear Industry: 18th International Symposium, pp.240-280, 2018. ,
URL : https://hal.archives-ouvertes.fr/hal-01702107
Embrittlement of pre-hydrided Zircaloy-4 by steam oxidation under simulated LOCA transients, Journal of Nuclear Materials, vol.469, pp.20-31, 2016. ,
URL : https://hal.archives-ouvertes.fr/hal-02557552
Influence of hydrogen on the oxygen solubility in Zircaloy-4, Journal of Nuclear Materials, vol.469, pp.228-236, 2016. ,
URL : https://hal.archives-ouvertes.fr/cea-01261954
Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions, Nuclear Engineering and Design, vol.283, pp.33-39, 2015. ,
Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident, Nuclear Engineering and Design, vol.301, pp.366-377, 2016. ,
The H-Zr (hydrogen-zirconium) system, Bulletin of Alloy Phase Diagrams, vol.11, issue.4, pp.385-395, 1990. ,
Study of secondary intermetallic phase precipitation/dissolution in Zr alloys by high temperature?high sensitivity calorimetry, Journal of Nuclear Materials, vol.372, issue.2-3, pp.367-378, 2008. ,
URL : https://hal.archives-ouvertes.fr/cea-02355390
A thermodynamic database for zirconium alloys, Journal of Nuclear Materials, vol.275, issue.3, pp.287-295, 1999. ,
Experimental investigations and thermodynamic modelling of the Cr?Nb?Sn?Zr system, Calphad, vol.64, pp.43-54, 2019. ,
URL : https://hal.archives-ouvertes.fr/cea-02339676
Quantification and local distribution of hydrogen within Zircaloy-4 PWR nuclear fuel cladding tubes at the nuclear microprobe of the Pierre Süe Laboratory from ?-ERDA, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, vol.266, issue.10, pp.2424-2428, 2008. ,
In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature, Journal of Nuclear Materials, vol.458, pp.245-252, 2015. ,
In Situ Characterization of Lattice Structure Evolution during Phase Transformation of Zr-2.5Nb, Advanced Engineering Materials, vol.13, issue.9, pp.882-886, 2011. ,
Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction, Journal of Nuclear Materials, vol.392, issue.3, pp.453-463, 2009. ,
Hydride precipitation in ?/? zirconium alloys, Acta Metallurgica, vol.31, issue.9, pp.1381-1391, 1983. ,
Identification and characterization of a new zirconium hydride, Journal of Microscopy, vol.232, issue.3, pp.410-421, 2008. ,
URL : https://hal.archives-ouvertes.fr/hal-02395459
Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System, Zirconium in the Nuclear Industry: Thirteenth International Symposium, p.361-361-23 ,
ASTM standards on environmental sampling, 2nd ed. ASTM (American Society For Testing and Materials), ASTM, west Conshohocken, PA, (1997), 1010 Pages, [ISBN No.:0-8031-1835-X], U.S. List Price: $99.00, Environmental Progress, vol.18, issue.1, pp.S7-S7, 1999. ,
A profile refinement method for nuclear and magnetic structures, Journal of Applied Crystallography, vol.2, issue.2, pp.65-71, 1969. ,
Modélisation du comportement mécanique "post-trempe", après oxydation à haute température, des gaines de combustible des réacteurs à eau pressurisée, MINES ParisTech, 2012. ,
Correction of intensities for preferred orientation in powder diffractometry: application of the March model, Journal of Applied Crystallography, vol.19, issue.4, pp.267-272, 1986. ,
Coefficients of Thermal Expansion for Zirconium, JOM, vol.6, issue.9, pp.1045-1052, 1954. ,
Determination des coefficients principaux d'expansion thermique du Zr ?, Journal of Nuclear Materials, vol.20, issue.1, pp.75-82, 1966. ,
Lattice Parameters, Thermal Expansions, and Grüneisen Coefficients of Zirconium, 4.2 to 1130°K, Physical Review, vol.144, issue.2, pp.478-484, 1966. ,
Thermal and mechanical properties of zirconium hydride, Journal of Alloys and Compounds, vol.293-295, pp.23-29, 1999. ,
The preparation of Zr-deuteride and phase stability studies of the Zr-D system, Journal of Nuclear Materials, vol.485, pp.243-252, 2017. ,
Thermal Expansion of Zirconium between 298°K and 1600°K, The Journal of Chemical Physics, vol.21, issue.8, pp.1383-1384, 1953. ,
The temperature dependence of the lattice parameters of pure BCC Zr and BCC Zr-2 at.%Co, Journal of Physics: Condensed Matter, vol.4, issue.3, pp.727-733, 1992. ,
Structural properties and stability of metastable phases in the Zr-Nb system: Part II. Aging of bcc (?) alloys and assessment of ?-Zr, Metallurgical and Materials Transactions A, vol.34, issue.12, pp.2771-2779, 2003. ,
Structural properties and stability of metastable phases in the Zr-Nb system: Part II. Aging of bcc (?) alloys and assessment of ?-Zr, Metallurgical and Materials Transactions A, vol.34, issue.12, pp.2771-2779, 2003. ,
Thermal equations of state of the?,?, and?phases of zirconium, Physical Review B, vol.71, issue.18, p.184119, 2005. ,
The nature of the ?-phase in zirconium-hydrogen alloys, Journal of the Less Common Metals, vol.35, issue.1, pp.177-179, 1974. ,
Formation of the gamma phase by a peritectoid reaction in the zirconium-hydrogen system, Journal of Nuclear Materials, vol.45, issue.3, pp.235-244, 1972. ,
The relationship between gamma and delta hydrides in zirconium-hydrogen alloys of low hydrogen concentration, Journal of Nuclear Materials, vol.49, issue.3, pp.262-280, 1974. ,
An electron optical study of hydride precipitation and growth at crack tips in zirconium, Acta Metallurgica, vol.28, issue.9, pp.1215-1221, 1980. ,
Kinetics of the ? to ? zirconium hydride transformation in Zr-2.5Nb, Acta Materialia, vol.51, issue.7, pp.2041-2053, 2003. ,
Observation of kinetics of ? zirconium hydride formation in Zr?2.5Nb by neutron diffraction, Journal of Nuclear Materials, vol.256, issue.2-3, pp.102-107, 1998. ,
Observations of temperature stability of ?-zirconium hydride by high-resolution neutron powder diffraction, Journal of Alloys and Compounds, vol.661, pp.55-61, 2016. ,
Observations of temperature stability of ?-zirconium hydride by high-resolution neutron powder diffraction, Journal of Alloys and Compounds, vol.661, pp.55-61, 2016. ,
The preparation of Zr-deuteride and phase stability studies of the Zr-D system, Journal of Nuclear Materials, vol.485, pp.243-252, 2017. ,
Electron microscope observations on the precipitation of zirconium hydride in zirconium, Acta Metallurgica, vol.11, issue.4, pp.267-280, 1963. ,
Oxygen, Hydrogen and Main Alloying Chemical Elements Partitioning Upon Alpha??Beta Phase Transformation in Zirconium Alloys, Solid State Phenomena, vol.172-174, pp.753-759, 2011. ,
Hydrogen and Main Alloying Chemical Elements Partitioning Upon Alpha-Beta Phase Transformation in Zirconium Alloys. Solid State Phenomena, pp.753-759, 2011. ,
Variations des paramètres cristallins de la solution solide a zirconiumoxygène en fonction de la teneur en oxygène. Comptes Rendues de l'Académie Des Sciences, vol.269, pp.587-590, 1969. ,
Investigations of the Microstructure and Mechanical Properties of Prior-? Structure as a Function of the Oxygen Content in Two Zirconium Alloys, Zirconium in the Nuclear Industry: 15th International Symposium, p.71-71-20 ,
URL : https://hal.archives-ouvertes.fr/hal-00488994
Investigations of the Microstructure and Mechanical Properties of Prior-? Structure as a Function of the Oxygen Content in Two Zirconium Alloys, Journal of ASTM International, vol.5, pp.1-20, 2008. ,
URL : https://hal.archives-ouvertes.fr/hal-00488994
Relationship between Crystallographic Texture and Dilatometric Behaviour of a Hexagonal Polycrystalline Material, Materials Science Forum, vol.273-275, pp.529-534, 1998. ,
Atomic-scale Ab-initio study of the Zr-H system: I. Bulk properties, Acta Materialia, vol.50, issue.13, pp.3513-3526, 2002. ,
URL : https://hal.archives-ouvertes.fr/hal-01828674
Hydrogen and vacancy clustering in zirconium, Acta Materialia, vol.102, pp.56-69, 2016. ,
URL : https://hal.archives-ouvertes.fr/cea-02385740
Hydrogen and vacancy clustering in zirconium, Acta Materialia, vol.102, pp.56-69, 2016. ,
URL : https://hal.archives-ouvertes.fr/cea-02385740
Hydrogen contribution to the thermal expansion of hydrided Zircaloy-4 cladding tubes, Journal of Nuclear Materials, vol.440, issue.1-3, pp.169-177, 2013. ,
URL : https://hal.archives-ouvertes.fr/hal-00830844