, Or, on identifie des bulles volumineuses et des petites bulles dans la zone 3 qui n'entraînent pas de modification du paramètre S par rapport au bulk déterminé par PAS
, une des hypothèses pouvant être émises repose sur une pression différente des bulles suivant leur localisation dans l'échantillon et que cette pression influence la mesure PAS. Cette hypothèse est corroborée, d'une part par les études de Saito et al.] qui ont montré que le taux de conversion o-Ps ' p-Ps dépend de la pression du gaz utilisé (xénon dans leur expérience) et d'autre part, 2006.
, Zone 3) pourraient se dépressuriser via plusieurs mécanismes décrits par, 1991.
, irradiation a un impact important sur le relâchement des gaz de fission dans UO 2 pour les températures inférieures à 1400 °C. Dans le combustible, deux types d'interactions sont susceptibles d'entraîner la migration du xénon : les chocs balistiques et les excitations électroniques. Pour simuler les chocs balistiques, nous avons irradié les échantillons avec des ions argon de 800 keV
, >%2-4444444444444444444444444444444444444444444444444444-5M:! "[#$#! Q&'1-&'!9-,<*2*+4*-&'!i!*--43*4, 4R&:!3&'!*)+'!*)3&!3&!$B8!Q&[! ! 6666! $BJ! "[#8#! "--43*4/*)+!4R&:!*)+'!*)3&!3&!$78!Q&[! ! 666666666666666666666666666! $I$!
, 4444444444444444444444444444444444444444444444444444444444444444444444-5::! 5.6-'30, )68'(+## 9##6+,.1)30.*#7+11+,# 7+# <=*.* >)68'(+ ?3'3#0*030
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, Radiation stability of fluorite-type nuclear oxides Grain boundaries as point defect sources or sinks?Diffusional creep Atomistic modelling of the vibrational and thermodynamic properties of uranium dioxide, UO 2 Rapport énergie 2050 Rapport du ministère de l'économie, des finances et de l'industrie In-pile Xe diffusion coefficient in UO 2 determined from the modeling of intragranular bubble growth and destruction under irradiation On the solution and migration of single Xe atoms in uranium dioxide ?an interatomic potentials study Molecular dynamics study of Xe bubbles re-solution in UO 2, Nuc. Inst. Meth. B Acta Metallurgica J. Nucl. Mater. J. Nucl. Mater. J. Nucl. Mater, vol.266, issue.374, pp.2842-2847, 1979.
, The role of vacancies and dislocations in the nucleation and growth of gas bubbles in irradiated fissile material Characterizing the relationship between hyperstoichiometry, defect structure and local corrosion kinetics of uranium dioxide Kinetics of precipitation of U 4 O 9 from hyperstoichiometric UO 2+x Burnup dependence of melting temperature of FBR mixed oxide fuels irradiated to high burnup Migration behavior of iodine in nuclear fuel Molecular dynamic simulation of fission fragment induced thermal spikes in UO 2 : Sputtering and bubble re-solution Interaction ionssurfaces : étude de la pulvérisation du fluorure de lithium LiF par technique d'imagerie XYTOFSIMS " Thèse Université de Caen Basse Normandie (2011) I [IDRISS 2010] H. Idriss Surface reaction of uranium oxide powder, thin film and single crystals First- Principles calculation of point defect in uranium dioxide, J. Nucl. Mater. Electrochimica Acta J. Nucl. Mater J. Nucl. Mater. J. Nucl. Mater. J. Nucl. Mater Surface Science Report World Enegy Statistics World Energy Outlook Materials Transactions, vol.100, issue.47 11, pp.251914-305, 1956.
, Temperature dependence of diffusivity of xenon in high dose irradiated UO 2 Difficulty of dislocation-punching from densely distributed high-pressure bubbles " , Radiation effects and defects in solids Formation and growth of intragranular fission gas bubbles in UO 2 fuels with burnup of 6-83 GWd/tU Diffusion coefficient of Xe-133 in SIMFUEL with a low burnup The chemical state of fission products in oxide fuels Fundamentals of positron annihilation spectroscopy and its application in semiconductor " cours donné à " International School of Positron Studies, UO 2 : Part 1 Etude des défauts surfaciques et volumiques induits par les ions lourds dans les isolants Doctorat de l'université de Caen, soutenue le 21 octobre 2003, pp.161-166, 1985.
, Vacancy defects induced in sintered polished UO2 disk by helium implantation Thermal evolution of the vacancy defects distribution in 1 MeV helium implanted sintered UO 2 Fission product release from nuclear fuel by recoil and knockout Chemical thermodynamic representation of UO 2±x 473-488 M [MACEWAN 1964 Xenon diffusion in UO 2 , Some complicating factors Growth of inert gas bubbles after implantation XAS characterization of Xenon bubbles in uranium dioxide Effect of the cascade energy on defect production in uranium dioxide Radiation Damage in Crystalline Insulators, Oxides and Ceramic Nuclear Fuels Erratum : Surface damage in UO2 due to mechanical polishing and ion bombardment A channeling study of ion implantation damage in UO 2 and UN Damage recovery in the U-Sublattice of ion implanted UO 2 between 5K and Radiation damage in nuclear materials Polygonization of single crystals of the fluorite-type oxide UO2 due to high dose ion implantation Formation of the rim structure in high burnup fuel A review of the oxidation of uranium dioxide at temperatures below 400°C, Suivi et maîtrise du vieillissement des matériaux des installations nucléaires " , présentation aux journées techniques AFIAP, 13 octobre Diffusion in doped UO 2] Hj. Matzke, P.G. Lucuta, T. Wiss " Swift heavy ion and fission damage effects in UO 2 " Nucl. Inst. Meth. Phys. Res, pp.159-168, 1964.
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, Spin-Orbit Quenching of Positronium during Atomic Collisions, Physical Review Letters, vol.90, issue.18, pp.90-108, 2003.
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, Energie, électricité et nucléaire Depth profiles of damages accumulation in UO 2 and (U,Gd)O2 pellets irradiated with 100 MeV iodine ions MARGARET: A comprehensive code for the description of fission gas behaviour Polytypic arrangements of cuboctahedral oxygen cluster in U 3 O 7 Re-solution of fission gas ? A review: Part I. Intragranular bubbles Diffusion thermique et sous irradiation du chlore dans le dioxyde d'uranium Chlorine diffusion in uranium dioxide under heavy ion irradiation Secondary ion mass spectrometry of irradiated nuclear fuel and cladding: An overview Release of fission products, and Tc) from polycristalline UO 2 Q [QUENTIN 2010] A. Quentin " Modifications structurales de spinelles sous irradiation, pp.126-135, 1789.
, Transmission electron microscopy study of fission product behavior in high burnup UO 2 Dynamics of irradiation-induced grain subdivision and swelling in U 3 Si 2 and UO 2 fuels In situ TEM study of temperature-induced fission product precipitation in UO 2 Thermal diffusion of iodine in UO 2 and UO 2+x, Experimental Evidence for Spin-Orbit Interactions in Positronium-Xe Collisions, pp.90-95, 1992.
, Sources of Thermally Generated Vacancies in Single-Crystal and Polycrystalline Gold Optical properties of a mechanically polished and airequilibrated [111] UO 2 surface by Raman and ellipsometric spectroscopy LLNL-PROC-415099 Solide state physics 2 Phase-field modeling of gas bubbles and thermal conductivity evolution in nuclear fuels Transmission electron microscopy observation on irradiation-induced microstructural evolution in high burn-up UO 2 disk fuel Clarification of high density electronic excitation effects on the microstructural evolution in UO 2 A calculation of the migration of fission gas in material precipitation and resolution of gas atoms under irradiation Matrix swelling rate and cavity volume balance of UO 2 fuels at high burn-up Test of the hypothesis of transient molten state diffusion for swiftheavy-ion induced mixing Atomic Scale Disorder in Fluorite and Fluorite Related Oxides These soutenue à l'imperial college of Science SiO 2 sur silicium : comportement sous irradiation avec des ions lourds Thèse de l'université de Caen Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels 8-18 T [TANDEM 2012] site internet de du Tandem de l'IPNO http://ipnweb.in2p3.fr/tandem- alto/tandem/index Oxidation of UO 2 fuel pellets in air at 503 and 543 K studied using X-Ray photoelectron spectroscopy and X-Ray diffraction Condensed-phase xenon and krypton in UO 2 spent fuel First-principles study of noble gas impurities and defects in UO 2 Thermal spike model in the electronic stopping power regime Transient thermal processes in heavy ion irradiation of crystalline inorganic insulators Nanometric transformation of the matter by short and intense electronic excitation: Experimental data versus inelastic thermal spike model The spacing of intergranular fission gas bubbles in irradiated UO 2 The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide Background and Derivation of ANS-5.4 Standard Fission Product Release Model Recovery stages in UO 2 at low temperatures Radiation defects in the oxygen sublattice of UO 2 single crystals Effects of additives and the oxygen potential on the fission gas diffusion in UO 2 fuel Etude des mécanismes microstructuraux liés au relâchement des gaz de fission du dioxyde d'uranium irradié Displacement cascade initiated with the realistic energy of the recoil nucleus in UO 2 matrix by molecular dynamics simulation Multiscale modelling for the fission gas behaviour in the TRANSURANUS code Atomic diffusion mechanism of Xe in UO 2 Phonon spectrum, thermal expansion and heat capacity of UO 2 from first principles Effects of pellet microstructure on irradiation behavior of UO 2 fuel Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases Evaluation of phonon-level density of UO 2 by molecular dynamics simulation The stopping and range of ions in solids, photoelectron spectroscopy study of anodically oxidized SIMFUEL surfaces UO 2 single crystals : A TEM Thèse soutenue à l'Institut National Polytechnique de Grenoble le 4 octobre Defect energetic and Xe diffusion in UO 2 and ThO 2] I. Zacharie, S. Lansiart, P.Combette, M. Trotabas, M.Coster, M. Groos, pp.1863-1873, 1956.
, 53'7&80'653E<";;"53'7&'GC > '=0%';&62&$%'79062"U"2:'&3'>IIM'ASDCNEVE'>I(>K' LLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLL' >I! !"#$%&'()?'*'W$032"2:'7&'GC > ':T$"U08&32':<";&'=0%'XF/'=%57$"2'&3'45362"53'7&'80';5$%6&'7O:3&%#"&'=%"<0"%&'AFE,YYEN' >IIQKZ'[&;'"36&%2"2$7&;';532'%&8":&;'0$\'U0%"02"5344:%&32&;':2$7&";:'703;'8&;'NE+'ASNEcSK'f'd1e44:%&32&, ()Q*'+%57$62"53':8&62%"T$&'795%ES'>I(()>K' LLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLL' >>! !"#$%&'()M'*'+%57$62"53'25208&'79:8&62%"6"2:'&3'!%036&'7&=$";'(PQI'A_Cbc'>I(>K' LLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLL' >R! !"#$%&'(<0'79$3'6%0@53'6532&3032'8&;' =0;2"88&;'7&'65<1$;2"18&'A-[S,N'>IIMK'LLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLL' >?! !"#$%&'()(('*'+%54"8;'7&'2&<=:%02$%&'%:#3032'g'89"32:%"&$%'7O$3&'=0;2"88&'7&'65<1$;2"18&'%&=%:;&32:;'=5$%'7, pp.0-2
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, 8O:6/032"8853'_/'%&6$"2'M'/e`'5$'$3&'5\@702"53'85608";:&' d<&;$%:'=0%'h&'&2'08Z'Ah&'>I(IK'&2'=%:;&32:'&31è'5$'=0%'890$#<&3202"53'7&'80';$%406&'8
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