.. Variables, 49 3.2.4 Neutron transport equation 49 3.2.5 Isotopic and precursor evolutions, Boundary conditions, p.58

A. Numerical-methods-core-calculation and .. , 59 3.3.1 Code Description, 59 3.3.2 Symbols and definitions, p.60

.. Multigroup-theory, 61 3.3.5 Microscopic Cross Sections, p.67

.. Power, 1 Burn-up computation, .3.2 Flux and radial Power Computation at the pellet scale . . . . . 88 4.3.3 Prompt neutron flux computation for the, p.89

.. Neutronics-conclusion, 93 x 20.2. LOCAL HOT SPOT PARAMETERS COUPLING COMPARISONS 20.2 Local Hot Spot parameters coupling comparisons Figure 20.10. Local Hot Spot Power evolution couplings comparison [1] CASL Project : http://www.casl.gov

S. Abide and F. Caro, Maquette solveur volumes finis multi-physique, CEA Report DEN, pp.7-12, 2007.

S. Aniel, E. Royer, and P. Ferraresi, Calculation of a Reactivity Initiated Accident with a 3D Cell-by-Cell Method: Application of the SAPHYR System to a Rod Ejection Accident in TMI1, 2001.

S. Aniel, A. Bergeron, P. Fillion, D. Gallo, F. Gaudrier et al., FLICA4: Status of numerical and Physical models and overview of applications, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH- 11) Popes Palace Conference Center American nuclear society, 1985.

F. Auria, A. Bousbia-salah, A. Petruzzi, A. Del, and . Nevo, State of the art in using Best Estimate calculation tool in Nuclear technology, Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, 2006.

M. Avramova, K. Ivanov, T. Kozlowski, I. Pasichnyk, W. Zwermann et al., Multi-physics and multi-scale benchmarking and uncertainty quantification within OECD/NEA framework, Annals of Nuclear Energy, vol.84, pp.178-196, 2015.
DOI : 10.1016/j.anucene.2014.12.014

URL : https://doi.org/10.1016/j.anucene.2014.12.014

A. Avvakumov, V. Malofeev, and V. Sidorov, Analysis of Pin-by-Pin Effects for LWR Rod Ejection Accident, 2000.

H. Bailly, D. Menessier, and C. Prunier, Le combustible nucléaire des réacteur à eau sous pression et des réacteur à neutrons rapides, conception et comportement, p.688, 1997.

. Bateman, Solution of a system of differential equations occuring in the theory of radioactive transformations, Proceedings, pp.423-427, 1910.

F. Barre, O. Marchand, Y. Monerie, and F. Perales, Advanced modelling of complex material properties -a significant step towards predictive computation of cladding rupture, EUROSAFE forum, 2010.

A. M. Baudron, J. J. Lautard, and . Minos, Solver for Core Calculation, Nuclear Science and Engineering, vol.144, issue.3, pp.250-263, 2007.
DOI : 10.13182/NSE03-A2340

A. M. Baudron and J. J. Lautard, Simplified PN Transport core calculation in the APOLLO3 system, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, 2011.
DOI : 10.13182/nse07-a2660

]. R. Beauwens, Théorie des réacteurs nucléaires I, 2004.

R. Benjamen, . Jr, and . Strong, Properties of steam and water interactive desk, Reference NBS/NRC IAPS'84, IMPULES engineering San Francisco, 1984.

A. A. Bishop, R. O. Sandberg, and L. S. Tong, Forced convection heat transfer at high pressure after the critical heat flux, 1965.

G. Bois and D. /. Nt, Analyse de schémas de diffusion pour les maillages non-conforme dans FLICA4: implementation et éléments de validation, pp.13-20, 2007.

D. , S. /. Letr, and . Rt, BOUDSOCQ, Fonctions d'état de l'eau pour le code FLICA4, pp.99-2594, 2000.

J. Brachet, L. Portier, T. Forgeron, J. Hivroz, D. Hamon et al., Influence of hydrogen content on the ?/? phase transformation temperatures and on the thermal-mechanical behavior of Zy4, M4 (ZrSnFeV), and M5TM (ZrNbO) alloys during the first phase of LOCA transient, 13th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1423, pp.673-701, 2002.

J. Brochard, Modelling of Pellet Cladding Interaction in PWR Fuel, 2001.

G. B. Bruna, F. Fouquet, F. Dubois, J. Le-pallec, E. Richebois et al., HEMERA: a 3D coupled core-plant system for accidental reactor transient simulation, ICAPP 2007 Proceedings, Paper 7205, 2007.

]. R. Capanna, Contribution to the development of a calculation scheme into the code APOLLO3 ®dedicated to the modelling of an accident scenario of type RIA in a nuclear power plant, 2014.

]. A. Casenave, Etude d'un Schéma de calcul pour la détermination des sections efficaces d'un coeur de REP, 2012.

B. Cazalis, J. Desquineses, C. Poussard, M. Petit, Y. Monerie et al., The PROMETRA Program: Fuel Cladding Mechanical Behavior under High Strain Rate, Nuclear Technology, vol.16, issue.3, pp.215-229, 2007.
DOI : 10.1007/BF02814242

B. Cazalis and V. Georgenthum, MOX fuel behavior under reactivity initiated accident, Top Fuel -reactor fuel performance, Manchester, United Kingdom, 2-6 sept. 2012 BIBLIOGRAPHY [39] CEA, La neutronique -Les méthodes de la neutronique, Commissariat à l'Energie Atomique et aux Energies Alternatives (CEA, 2013.

]. S. Chauvet, Méthode multi-échelle pour la résolution des équations de la cinétique neutronique, Thése de Doctorat, p.348435, 2008.

B. Chanaron and A. , Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project, Annals of Nuclear Energy, vol.84, pp.166-177, 2015.
DOI : 10.1016/j.anucene.2014.12.013

]. P. Chemin, Approximation des tables de l'eau, 2003.

]. S. Chemin, D. Coupling, and D. , 13 : New FLICA version for New Salome interface for FLICACRONOS coupling and data exchange with SCANAIR, NURESAFE, D11, 2014.

]. S. Chemin and D. , 11 : Specifications for SCANAIR Integration D11.12 : Specifications CEA coupling in-core, NURESAFE Collaborative Project, D11.11 and D11.12, 2014.

]. D. Chisholm, Friction during the two flow of Two-Pase Mixtures in Smooth tubes and channels, NEL Report, vol.529, 1972.

H. Chu, S. Wu, K. Chien, and R. Kuo, Effect of radial hydrides on the axial and hoop mechanical properties of Zircaloy-4 cladding, Journal of Nuclear Materials, vol.362, issue.1, pp.93-103, 2007.
DOI : 10.1016/j.jnucmat.2006.11.008

J. G. Collier, J. A. Ward, K. T. Claxton, and D. Chislon, Heat transfer and fluid flow servive, 1972.

J. G. Collier and J. R. Thome, Convective boiling and condensation, Third edn, 1994.

]. E. Contestiu, Description of creep-plasticity interaction with non-unified constitutive equation, Nuclear engineering design, pp.265-80, 1989.

D. E. Cullen, Application of the Probability Table Method to Multigroup Calculations of Neutron Transport, Nuclear Science and Engineering, vol.55, issue.4, pp.387-400, 1974.
DOI : 10.13182/NSE74-3

D. E. Cullen and G. C. Pomraning, The multiband method in radiative transfer calculations, Journal of Quantitative Spectroscopy and Radiative Transfer, vol.24, issue.2, pp.97-117, 1980.
DOI : 10.1016/0022-4073(80)90024-2

A. Dall, D. Osso, and . Tomatis, Section Efficaces à AREVA: Présent et passé, pp.11-2012

R. Daum, S. Majumbdar, W. Liu, and M. Billone, Radial-hydride Embrittlement of High-burnup Zircaloy-4 Fuel Cladding, Journal of Nuclear Science and Technology, vol.67, issue.3, pp.1054-1067, 2006.
DOI : 10.1016/0022-3115(72)90021-9

R. Dautray and J. L. Lions, Analyse mathématique et calcul numérique pour les sciences et les techniques, 1987.

J. Desquines and J. Fleurot, The fracture and spallation of zirconia layers in high burnup PWR fuel claddings submitted to RIA transients, 18th International Conference on Structural Mechanics in Reactor Technology, pp.444-453

D. J. Diamond, C. Y. Yang, and A. L. Aronson, Estimating the Uncertainty in Reactivity Accident Neutronic Calculations, Proceedings of the Twenty-Sixth Water Reactor Safety Information Meeting, 1998.

D. J. Diamond, Intercomparison of Results for a PWR Rod Ejection Accident, Proceedings of the Twenty-Seventh Water Reactor Safety Information Meeting, Nuclear Engineering and Design, vol.208, 1999.

D. J. Diamond, B. P. Bromley, and A. L. Aronson, Studies of the Rod Ejection Accident in PWR, 2002.

T. J. Downar, Coupled Codes for Multi-Physics Nuclear Reactor Simulation, Thesis, 2006.

J. J. Duderstadt, L. J. Hamilton, J. Wiley, and S. , Nuclear Reactor Analysis

M. S. Ellis, J. Watson, and K. Ivanov, Progress in the development of an implicit steady state solution in the coupled code TRACE/PARCS, Progress in Nuclear Energy, vol.66, pp.1-12, 2013.
DOI : 10.1016/j.pnucene.2013.02.009

R. Eymard, T. Gallouet, and R. Herbin, The finite volume method, Handbook for Numerical Analysis, Ph. Ciarlet, J.L. Loins eds, pp.715-1022, 2000.

]. I. Faille, A control volume method to solve an elliptic equation on a two-dimensional irregular mesh, Computer Methods in Applied Mechanics and Engineering, vol.100, issue.2, pp.275-290, 1992.
DOI : 10.1016/0045-7825(92)90186-N

R. M. Ferencz, Nuclear Energy Advanced modelling and Simulation (NEAMS) Structural Mechanics Module Development Plan, Methods Development Group, 2013.
DOI : 10.2172/1113412

. Ph, D. Fillion, S. Caruge, and . Clerc, FLICA4: an advanced code for two-phase flow parallel computing, pp.3-8, 1999.

P. Fillion, A. Chanoine, S. Dellacherie, A. Kumbaro, and . Flica-ovap, FLICA-OVAP: A new platform for core thermal???hydraulic studies, Nuclear Engineering and Design, vol.241, issue.11, pp.4348-4358, 2011.
DOI : 10.1016/j.nucengdes.2011.04.048

. Ph, A. Fillion, D. Bergeron, O. Gallo, E. Gregoire et al., FLICA4: Version 1.11.2 PUB, User guide, Reference manual of modules and proce- dures, CEA Report, 2013.

M. C. Fiorina, M. Au-fiero, S. Pelloni, and K. Mikityuk, A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, 2014.
DOI : 10.1115/ICONE22-30395

K. Forster and R. Greif, Heat transfer to a boiling liquid ; mechanism and correlations, 1958.
DOI : 10.2172/4298039

T. Fuketa, F. Nagase, K. Ishijima, T. Fujishiro, and N. /. , RIA experiments with high burnup PWR fuels, Nuclear Safety, vol.37, issue.4, pp.328-342, 1996.
DOI : 10.1016/s0022-3115(97)00173-6

T. Fuketa, H. Sasajima, Y. Mori, and K. Ishijima, Fuel failure and fission gas release in high burnup PWR fuels under RIA conditions, Journal of Nuclear Materials, vol.248, pp.249-256, 1996.
DOI : 10.1016/S0022-3115(97)00173-6

F. , N. Sasajima, U. Nagase, and A. Kikuchi, Behavior of PWR and BWR fuel during Reactivity-initiated accident conditions, Proc. ANS topical meeting on light water reactor fuel performance, 2000.

T. Fuketa, H. Sasajima, and T. Sugiyama, Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding under Reactivity-Initiated-Accident Conditions, Nuclear Technology, vol.270, issue.1, pp.50-62, 2001.
DOI : 10.1016/S0022-3115(98)00895-2

T. Fuketa, H. Sasajima, T. Sugiyama, and N. Nakamura, Effect of pellet expansion and cladding hydrides on PCMI failure of high burn-up LWR fuel durin reactivity transients, Nuclear safety research conference, 2003.

. Ph, C. Garcia, M. Struzik, and . Agard, The Effect of Fission Gas Swelling on Cladding Strains During Power Ramp Tests Fuel Chemistry and Pellet Cladding Interaction Related to High Burn-Up Fuel, Proc. Conf, 1998.

A. M. Garde, G. P. Smith, and R. C. Pirek, Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy4, Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, pp.407-430, 1996.

J. M. Gatt and J. C. Menard, Overall viscoplastic behaviour of uranium dioxide, Transactions, SMiRT, vol.19, 2007.

V. Georgenthum, J. Desquine, and V. Bessiron, Influence of Outer Zirconia Transient Cracking and Spalling on Thermomechanical Behaviour of High Burnup Fuel Rod Submitted to RIA, Journal of Nuclear Science and Technology, vol.337, issue.11, pp.1089-1096, 2006.
DOI : 10.1016/S0921-5093(01)01991-8

F. N. Gleicher, B. Spencer, S. Novascone, R. Williamson, R. C. Mar-tineau et al., Coupling the Core Analysis Program DeCART to the Fuel Performance Application, 2013.

H. Golfier, R. Lenain, C. Calvin, J. Lautard, A. Baudron et al., APOLLO3: a common project of CEA, AREVA and EDF for the development of a new deterministic multi-purpose code for core physics analysis, International Conference on Mathematics, Computational Methods and Reactor Physics, 2009.

S. K. Godunov, Finite difference method for numerical computation of discontinous solution of the equations of fluid dynamics (translated from Russian, Matematicheskii Sbornik, pp.47-271, 1959.

D. C. Groeneveld, The 1995 look-up table for critical heat flux in tubes, Nuclear Engineering and Design, vol.163, issue.1-2, p.163, 1996.
DOI : 10.1016/0029-5493(95)01154-4

C. R. Hann, Grapcom Thermal 1: A computer program for calculating the Gap conductance in oxide of fuel pins, p.1778, 1973.

D. L. Hetrick, Dynamics of Nuclear Reactors, 1971.

D. L. Hetrick, Dynamic of nuclear reactor, Amercian Nuclear society, pp.164-170, 1993.

M. Hursin, T. J. Downar, and B. Kochunas, Analysis of the Core Power Response during a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code, Nuclear Science and Engineering, vol.92, issue.9, pp.151-167, 2012.
DOI : 10.1080/18811248.2007.9711359

M. Hursin, T. J. Downar, and R. Montgomery, Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident, Nuclear Engineering and Design, vol.262, pp.180-188, 2013.
DOI : 10.1016/j.nucengdes.2013.04.023

]. M. Ishii, One-dimensional drift-flux model and constitutive equations for relative motion between phases in various two-phase flow, 1977.
DOI : 10.2172/6871478

K. Ivanov and M. Avramova, Verification and Validation analysis in multiphysics modelling for nuclear reactor design and safety, International Conference on Mathematics, Computational Methods and Reactor Physics, pp.on CD-ROM, 2009.

A. Ivanov, V. Sanchez, R. Stieglitz, and K. Ivanov, Internal multi-scale multi-physics coupled system for high fidelity simulation of light water reactors, Annals of Nuclear Energy, vol.66, pp.104-112, 2014.
DOI : 10.1016/j.anucene.2013.12.003

W. H. Jens and P. A. Lottes, Analysis of heat transfer burnout, pressure drop and density data for high pressure water, 1951.

L. O. Jernkvist, R. Ali, and P. R. Massih, A strain-based clad failure criterion for the RIA, 2004.

L. O. Jernkvist, R. Ali, and P. R. Massih, Assessment of fuel rod failure Threshols for reactivity initiated accidents, 2004.

J. Jimenez, M. Avramova, D. Cuervo, and K. Ivanov, Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis, International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource, 2008.

B. F. Kammenzind, D. G. Franklin, H. R. Peters, and W. J. Duffin, Hydrogen Pickup and redistribution in Alpha-annealed Zircaloy-4, 11th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1295. Garmisch-Partenkirchen, 1996.
DOI : 10.2172/10181237

]. J. Kearns, Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-4, Journal of Nuclear Materials, vol.22, issue.3, pp.292-303, 1967.
DOI : 10.1016/0022-3115(67)90047-5

G. R. Keeping, Physics of nuclar kinetics, pp.1965-435

E. H. Kennard, Kinetic theory of Gases, McCraw-Hill, p.314, 1938.

M. J. Koclas, A. Sissaoui, and . Hebert, Solution of the improved and generalized quasistatic methods using an analytic calculation or a semi-implicit scheme to compute the precursor equations, Annals of Nuclear Energy, vol.23, issue.11, 1995.
DOI : 10.1016/0306-4549(95)00075-5

A. J. Koning, Status of the JEFF Nuclear Data Library, AIP Conference Proceedings, 2007.
DOI : 10.1063/1.1944984

D. D. Lanning and C. R. Hann, Review of methods Applicable to the calculation of gap conductance in Zircaloy-cla UO2 fuel Rods, p.1894, 1975.

]. K. Lassman, Fuel-to-cladding heat transfer coefficient in a reactor fuel element, W??rme- und Stoff??bertragung, vol.6, issue.3-4, pp.185-202, 1979.
DOI : 10.1016/0029-5493(67)90111-2

K. Lassman and F. Hohlefeld, The revised URGAP model to describe the gap conductance between fuel and cladding, Nuclear Engineering and Design, vol.103, issue.2, pp.215-221, 1987.
DOI : 10.1016/0029-5493(87)90275-5

J. J. Lautard, D. Schneider, and A. M. Baudron, Mixed Dual Methods for Neutronic Reactor Core Calculation in the CRONOS System, Proc. ANS Topical Mtg., Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, 1999.

J. J. Lautard, A 3D nodal mixed dual method for nuclear reactor kinetics with improved quasistatic model and a semi-implicit scheme to solve the precursor equations, Annals of Nuclear Energy, vol.28, issue.8, pp.805-824, 2001.

]. F. Lemoine, High burnup fuel behavior related to fission gas effects under reactivity initiated accidents (RIA) conditions, Journal of Nuclear Materials, vol.248, pp.238-248, 1997.
DOI : 10.1016/S0022-3115(97)00157-8

F. Lemoine and M. Balourdet, RIA related analytical studies and separate effect tests, International Topical Meeting on Light Water Reactor Fuel Performance, 1997.

F. Lemoine, D. Bernard, and E. Federici, Validation assessment of neutron calculations for radial and azimuthal distributions of actinides and fission products in PWR rods, Water Reactor Fuel Performance Meeting, 2011.

]. R. Lenain, Modélisation axiale d'un coeur de réacteur à eau pressurisée pour l'étude d'un accident de reactivité : ejection d'une barre de contrôle, p.613

]. R. Lenain, Amélioration des méthodes de calcul de cÅ?urs de réacteurs nucléaires dans APOLLO3 : décomposition de domaine en théorie du transport pour des géométries 2D et 3D avec une accélération non linÃ?aire par la diffusion, 2015.

J. C. Le and . Pallec, Modélisation réaliste d'un accident de réactivité dans les REP et analyse d'incertitudes, 2002.

J. C. Le-pallec and C. /. Rt, Analyse d'un accident de réactivité induit par éjection d'une grappe sur un coeur REP1300 MWe chargé en combustible CORAIL, pp.3-3349, 2004.

J. C. Le-pallec, C. Poinot, N. Salanon, S. Crouzet, H. Zimmer et al., An evolutionary tool for PWR multithysics analysis in SALOME plate- form, Proceedings of ICAPP 2011, 2011.

J. C. Le-pallec, B. Michel, and C. /. Rt, Spécification du couplage entre APOLLO3 et ALCYONE pour le traitement d'un scénario de type RIA, pp.12-5453

J. C. Le-pallec, K. Mer, N. Nkonga, and . Crouzet, Neutronics/Fuel Thermomecanics Coupling in the Framework of a REA (Rod Ejection Accident) Transient Scenario Calculation, 2016.

P. Lesaint and P. A. Raviart, On a Finite Element Method for Solving the Neutron Transport Equation, Mathematical Aspects of Finite Elements in Partial Differential Equations, 1974.

M. Le and . Saux, Comportement et rupture de gaines en Zircaloy-4 détendu vierges hydrurées ou irradiées en situation accidentelle de type RIA, 2008.

A. L. Lindsay and L. A. Bromley, Thermal Conductivity of Gas Mixtures, Industrial & Engineering Chemistry, vol.42, issue.8, pp.1508-1511, 1950.
DOI : 10.1021/ie50488a017

O. Litaize and O. Serot, Investigation of phenomenological models for the monte carlo sinmulation of the prompt fission neutron and gamma emission, p.54616, 2010.

]. P. Magat, Analyse des techniques d'homogénéisation spatiale et énergétique dans la résolution de l'équation du transport des neutrons dans les réacteurs nucléaires, 1997.

J. W. Magedanz and M. N. Avramova, High-Fidelity Multi-Physics calculation for light water reactors using coupled CFT/TORT-TD:FRAPTRAN, Physor 2014, p.28, 2014.
DOI : 10.1016/j.anucene.2015.01.033

J. W. Magedanz, M. N. Avramova, and A. , High-fidelity multi-physics system TORT-TD/CTF/FRAPTRAN for light water reactor analysis, Annals of Nuclear Energy, vol.84, pp.234-243, 2015.
DOI : 10.1016/j.anucene.2015.01.033

V. S. Mahadevan, J. C. Ragusa, and C. Mousseau, A verification exercise in multiphysics simulations for coupled reactor physics calcula- tions, 2012.

H. Of, . Properties, . Use, . The, . Of et al., A, 1979.
URL : https://hal.archives-ouvertes.fr/hal-00200659

Z. R. Martinson and R. L. Johnson, Transient Irradiation of 1/4-Inch OD Zircaloy-2 Clad Oxide Fuel Rods to 590 cal/g UO2, IDO-ITR-102, Atomic Energy Division, 1968.

A. Mcminn, E. C. Darby, and J. S. Schofield, The Terminal Solid Solubility of Hydrogen in Zirconium Al-loys, Proceedings of the 12th International Symposium of the Zirconium in the Nuclear Industry, ASTM STP 1354, pp.173-195, 2000.

R. Meyer, R. Mccardell, H. Chung, D. Diamond, and H. Scott, A regulatory assessment of test data for reactivity initiated accidents, Nuclear Safety, vol.37, 1996.

]. B. Michel and . Sesc, Modelisation 3D de l'interface Pastille-Gaine (IPG): Location de la rupture et différenciation, 2006.

]. B. Michel and C. /. Nt, Introduction dans ALCYONE du modèle couplé fissuration-fluage Gatt Monerie, pp.6-052, 2007.

B. Michel, J. Sercombe, G. Thouvenin, and R. Chatelet, 3D fuel cracking modelling in pellet cladding mechanical interaction, Engineering Fracture Mechanics, vol.75, issue.11, pp.3581-3598, 2008.
DOI : 10.1016/j.engfracmech.2006.12.014

B. Michel, I. Ramiere, J. Sercombe, M. Agard, . Ch et al., PLEIADE: Multi concept nuclear fuel modelling, 2010.

B. Michel, C. Nonon, J. Sercombe, F. Michel, and V. Marel, Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment, Nuclear Technology, vol.238, issue.3, p.124, 2013.
DOI : 10.1016/j.nucengdes.2008.01.012

R. W. Miller and W. G. Lussie, The Response of UO2 Fuel Rods to Power Bursts, 5/16-Inch OD, Pellet and Powder Fuel, Zircaloy Clad, IDO-ITR-103, 1969.

]. A. Moal and D. , Report on SCANAIR-FLICA (CRONOS), NURESAFE, D11, 2014.

J. Y. Moller and J. J. Lautard, MINARET, a deterministic neutron transport solver for nuclear core calculations, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, pp.on CD-ROM, 2011.
URL : https://hal.archives-ouvertes.fr/cea-00545919

]. L. Mondelain, D. Schneider, and C. /. Rt, APOLLO3 : Premiers calculs 3D d'un coeur en évolution avec contre-réactions, pp.8-4613, 2008.

Y. Monerie and J. M. Gatt, Overall viscoplastic behavior of non-irradiated porous nuclear ceramics, Mechanics of Materials, vol.38, issue.7, p.608, 2006.
DOI : 10.1016/j.mechmat.2005.11.004

R. O. Montgomery and Y. R. Rashid, Evaluation of Irradiated Fuel During RIA-Simulation Tests, EPRI TR-106387, 1996.

R. Montgomery, J. Rashid, R. Dunham, O. Ozer, and S. Yagnik, The mechanical response of cladding with a hydride lens under PCMI loading conditions I, International Seminar on Pellet-Clad Interaction in Water Reactor Fuels, 2004.

]. P. Mosca, Conception et développement d'un mailleur énergétique adaptatif pour la génération des bibliothèques multigroupes des codes de transport, p.678561, 2012.

V. A. Mousseau, Implicitly balanced solution of the two-phase flow equations coupled to nonlinear heat conduction, Journal of Computational Physics, vol.200, issue.1, 2004.
DOI : 10.1016/j.jcp.2004.03.009

O. Mula and . Hernandez, Quelques contributions vers la simulation paralléle de la cinétique neutronique et la prise en compte de données observées en temps réel, p.1068691, 2014.

T. Nakamura, M. Yoshinaga, M. Takahashi, K. Okonogi, and K. Ishi-jima, Boiling water reactor fuel behavior under reactivity initiated accident conditions at burnup of 41 to 45 GWd/tonneU, Nuclear Technology, vol.129, 2000.

. Nea, . Neutronic, and . No, Thermohydraulics coupling in LWR technology: state-of-the art report, REAC-SOAR), vol.2, issue.5436, 2004.

. Nea and . Csni, Reactivity Initiated Accident (RIA) Fuel CodeBenchmark Phase II Simplified Cases Results, Summary and Analysis, 2016.

. Nea and . Nsc, Pressurized Water Reactor MOX/UO2 Core Transient Benchmark, Final Report, NEA n6048, 2006.

. Nea and . Nsc, Benchmark for Uncertainty analysis in modelling (UAM) for design, operation and safety analysis of LWRs, Volume II: Specification and support data for the core case (Phase II), 2016.

M. N. Nicolaev and V. F. Khokhlov, Systèmes des constantes en sous-groupes, INDC (CCP, 1969.

]. M. Nicolaev, Méthode des sous-groupes pour la prise en compte de la structure résonnante des sections efficaces dans les calculs neutroniques, Atomnaia Energia, 1970.

K. Nkonga, N. Crouzet, J. Le-pallec, B. Michel, D. Schneider et al., Coupling of fuel performance and neutronic codes for PWR, 11th World Congress on Computational Mechanics (WCCM XI) 5th European Conference on Computational Mechanics (ECCM V), 6th European Conference on Computational Fluid Dynamics (ECFD VI), 2014.

]. L. Noirot and M. -. , Description physique et numérique du modele de gaz applicable à chaque milieu homogène d'un combustible UO2 ou MOX, 2005.

]. L. Noirot and M. , A comprehensive code for the description of fission gas behavior Nucl, Eng. and Des, vol.241, pp.2099-2118, 2011.

]. O. Zerkak, Review of Multi-physics coupling techniques and suggestions of improvements in the context of NURISP, Collaborative Project (Large scale Integrating Project) Seventh Framework Programme EURATOM, 2009.

C. Ott and H. K. Kohl, Evaluation of a critical fuel rod enthalpy versus Burnup under reactivity insertion accident conditions, Annexe IV, Nuclear Energy safety, 1995.

]. L. Pagani, On the quantification of safety margins, Phd MIT, septembre, 2004.

I. M. Palmer, K. W. Hesketh, and P. A. Jackson, A model for predicting the radial power profile in a fuel pin, IAEA specialists meeting on water reactor fuel element performance computer modelling -Preston, 1992.

J. Papin, J. Melis, and C. Lecomte, Definition and Status of the CABRI International Program for High Burn-Up Fuel Studies, Proceedings of the Twenty-Eighth Water Reactor Safety Information Meeting, NUREG/CP-0172, U.S. Nuclear Regulatory Commission, pp.185-190, 2000.

]. J. Papin, Summary and Interpretation of the CABRI REP-Na Program, Nuclear Technology, vol.54, issue.3, 2007.
DOI : 10.1111/j.1151-2916.1971.tb12230.x

]. C. Patricot, Couplages multi-physiques : évaluation des impacts méthodologiques lors de simulations de couplages neutronique/ thermique/mécanique, Tel-01355622, 2016.

]. R. Pericas, Contribution to the validation of best estimate plus uncertainties coupled codes for the analysis of NK-TH nuclear transient, 2015.

R. Pericas, K. Ivanov, F. Reventos, and L. Batet, Code improvement and model validation for Asc??-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal???hydraulic code, Annals of Nuclear Energy, vol.87, pp.366-374, 2016.
DOI : 10.1016/j.anucene.2015.09.024

J. P. Piron, Météor Version 1.5.0, Notice de présentation, Note technique SDC, pp.96-2040, 1996.

]. G. Pomraning, Asymptotic and variational derivations of the simplified PN equations, Annals of Nuclear Energy, vol.20, issue.9, pp.623-637, 1993.
DOI : 10.1016/0306-4549(93)90030-S

P. Prevot, A. Nuttin, N. Capellan, and O. , MEPLAN Enhancements to the Nodal Drift Method for a Rod Ejection Accident in a PWR-like mini-core with lumped thermal model, Annals of Nuclear Energy, vol.101, issue.128â??138, 2017.

]. A. Racine, Influence de l'orientation des hydrures sur les modes de déformation, 2005.

V. H. Ransom and V. Mousseau, Convergence and accuracy of the RELAP5 two-phase flow model, ANS Topical Meeting on Advances in Mathematics, Computations and Reactor Physics, 1991.

Y. R. Rashid, Mathematical modeling and analysis of fuel rods, Nuclear Engineering and Design, vol.29, issue.1, pp.22-32, 1974.
DOI : 10.1016/0029-5493(74)90095-8

P. A. Raviart and J. P. Thomash, A Mixed Finite Element Method for the 2nd elliptic problems, Mathematical Aspects of the Finite Element Method, Lecture Notes in Mathematics, vol.606, 1977.

P. Raymond and I. Toumo, Numerical method for three-dimensional steady-state two-phase flow calculation, 1992.

W. H. Reed and T. R. Hill, Triangular Mesh Methods for Neutron Transport Equation, LA-UR-73-479, 1973.

P. Reuss-]-p, J. M. Ribon, and . Maillard, Précis de neutronique, Collection Génie Atomique, EDP science, Les tables de probabilité : Application au traitement des sections efficaces pour la neutronique, 1986.

S. Rt, RICHEBOIS, Données d'entrée des codes de calcul de coeur pour la modélisation d'une RTV d'un REP 1300MW, pp.2-003, 2004.

]. G. Rimpault, Algorithmic Features of the ECCO Cell Code for Treating Heterogeneous Fast Reactor Subassemblies, International Topical Meeting on Reactor Physics and Computations, 1995.

G. Rimpault, The ERANOS data and code system for fast reactor neutronic analyses, Proceedings of the International Conference on the New Frontier of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, PHYSOR

]. G. Roberts, The concentration of stress in cladding produced by the expansion of cracked fuel pellets, Nuclear Engineering and Design, vol.47, issue.2, p.257, 1978.
DOI : 10.1016/0029-5493(78)90068-7

E. Royer and I. Toumi, CATHARE-CRONOS-FLICA coupling with ISAS: A powerful tool for nuclear studies, ICONE-6 Meeting, 1998.

A. M. Rudling, Resonance absorption and non-uniform temperature distribution Annual review of information on Zircaloy technology : Loss of coolant accidents, LOCA, and reactivity initiated accidents, BWRs and PWRs, 1961.

]. P. Rubiolo, Modélisation du transfert thermique dans un milieu poreux : application aux réacteurs nucléaires en situation accidentelle, 2000.

C. Sartoris, A consistent approach to assess safety criteria for reactivity initiated accidents, Nuclear Engineering and Design, vol.240, issue.1, pp.57-70, 2010.
DOI : 10.1016/j.nucengdes.2009.10.025

]. F. Sauter, Modélisation du comportement viscoplastique du dioxyde d'uranium, 2000.

H. Sasajima, Fuel under Reactivity Initiated Accident Conditions, Journal of Nuclear Science and Technology, vol.37, issue.4, pp.1101-1104, 1999.
DOI : 10.1016/0022-3115(96)00374-1

R. Sanchez, I. R. Apollo, and . Sanchez, APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations, SAPHYR : A Code System from Reactor Design to Reference Calculations, International Conference on Supercomputing in Nuclear Applications, pp.352-362, 1988.
DOI : 10.13182/NSE80-04-481

D. Schneider, Mixed Dual Finite Element Method for the solution of the 3D kinetic Simplified PN transport equation, Nuclear Mathematical and Computational Sciences: A Century in Review, 2003.

D. Schneider, J. C. Le, A. Pallec, and . Targa, Mise en oeuvre d'un exercice de couplage APOLLO3-FLICA4 dans l'outil Multi Physique CORPUS dédié à lâ??analyse des réacteurs REP en situations de fonctionnement normal et accidentel, 2013.

D. Schneider, APOLLO3 ®: CEA/DEN deterministic multi-purpose code for reactor physics analy- sis, 2016.

F. Schmitz and J. Papin, High burnup effects on fuel behaviour under accident conditions: the tests CABRI REP-Na, Journal of Nuclear Materials, vol.270, issue.1-2, 1999.
DOI : 10.1016/S0022-3115(98)00895-2

. Sjenitzer, Coupling of dynamic Monte Carlo with thermal-hydraulic feedback, Annals of Nuclear Energy, vol.76, pp.27-39, 2015.
DOI : 10.1016/j.anucene.2014.09.018

G. Serre and M. Kaminaga, Physical laws of cathare revision 6. Pipe module, pp.98-136, 1999.

]. Dm2s, Séminaire Etudes multi-physiques Coeur et Piscines, 2016.

J. R. Shewchuk, Lecture Note on Delaunay Mesh Generation, BIBLIOGRAPHY Department of electrical Engineering and computer sciences, 2012.

M. Sladkoff, F. Huet, and A. Mocellin, Recommandation pour la loi de fluage stationnaire de l'UO2 non dopé: mise à jour de fin, 1998.

]. E. Smith, The Fuel-Cladding Interfacial Friction Coefficient in Water-Cooled Reactor Fuel Rods, Trans. SMIRT, vol.5, 1979.

]. A. Soniak, Irradiation Creep Behavior of Zr-Base Alloys, Zirconium in the Nuclear Industry, 13th International Symposium, ASTM STP 1423, p.837, 2002.

]. B. Spindler, Qualification du code FLICA-III M pour les calcules de thermohydrauliques de grappes et de coeurs de réacteurs à eau sous pression, pp.86-110, 1986.

Y. Sudo and M. Kaminaga, A New CHF Correlation Scheme Proposed for Vertical Rectangular Channels Heated From Both Sides in Nuclear Research Reactors, Journal of Heat Transfer, vol.115, issue.2, p.115, 1993.
DOI : 10.1115/1.2910695

T. Sugiyama and T. Fuketa, Effect of cladding pre-oxidation on rod coolability during reactivity accident conditions, In : Technical Committee Meeting on Fuel Behaviour Under Transient and LOCA Conditions, IAEA-TECDOC-1320, pp.102-110, 2001.

]. A. Targa, Contribution au developpement des schemas de couplage coeur neutroniquecombustible dedies à la realisation d'un scénario RIA (accident d'ejection de grappe de controle), Travail de fin d, 2013.

A. Targa, J. C. Le-pallec, P. Le, and . Tallec, Multiscale and multisolver pin power reconstruction approach in a reactor core calcu- lation, 2015.

A. Targa, J. C. Le-pallec, P. Le-tallec, K. Nkonga, N. Crouzet et al., Thermomechanics Best Estimate coupled approach in a Rod Ejection Accident core calculation, p.318, 2013.

P. K. Tondon and S. C. Saxena, Calculation of thermal conductivity of polar-nonpolar gas mixtures, Applied Scientific Research, vol.17, issue.1, pp.163-170, 1968.
DOI : 10.1007/BF00383919

K. Tomiyasu, T. Sugiyama, and T. Fuketa, Influence of Cladding-Peripheral Hydride on Mechanical Fuel Failure under Reactivity-Initiated Accident Conditions, Journal of Nuclear Science and Technology, vol.1, issue.4, pp.733-742, 2007.
DOI : 10.3327/jnst.41.37

L. S. Tong and J. Weisman, Thermal analysis of pressurized water reactors, 1996.

I. Toumi, Advanced numerical methods for two-phase flow simulation, OECD/NEA/CSNI workshop, pp.10-13, 2000.

I. Toumi, FLICA4: a three-dimensional two-phase flow computer code with advanced numerical methods for nuclear applications, Nuclear Engineering and Design, pp.139-155, 2000.

A. M. Torres, Further Developments of Multiphysics and Multiscale Methodologies for Coupled BIBLIOGRAPHY Nuclear Reactor Simulations, 2010.

A. M. Torres, V. H. Sanchez-espinoza, K. Ivanov, and R. Macian-juan, DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters ??? Part I: Development, implementation and verification, Annals of Nuclear Energy, vol.48, pp.108-122, 2012.
DOI : 10.1016/j.anucene.2012.05.011

A. M. Torres, V. H. Sanchez-espinoza, K. Ivanov, and R. Macian-juan, DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters ??? Part II: Comparison of different temporal schemes, Annals of Nuclear Energy, vol.48, pp.123-129, 2012.
DOI : 10.1016/j.anucene.2012.05.033

P. J. Turinsky, A Random Walk Toward Advanced modelling and Simulation Capabilities in Nuclear Engineering, NEAMS presentation, 2008.

P. J. Turinsky, Advances in Multi-physics and High performance computing in support of nuclear reactor power systems modelling and simulation, 2011.

A. C. Uggenti, Amélioration de la modélisation du combustible dans le cadre d'une description neutronique de type cinétique ponctuelle -analyses physiques en situation RIA, Ecole nationale supérieure de physique, électronique et matériaux (Phelma), 2014.

P. Vizcaino, A. Banchik, and J. P. Aabriata, Solubility of hydrogen in Zircaloy-4: irradiation induced increase and thermal recovery, Journal of Nuclear Materials, vol.304, issue.2-3, pp.96-106, 2002.
DOI : 10.1016/S0022-3115(02)00883-8

P. Vizcaino, A. Banchik, and J. P. Aabriata, Hydrogen in Zircaloyâ??4 : effects of the neutron irradiation on the hydride forma- tion, Journal of Nuclear Materials, vol.42, pp.6633-6637, 2007.

]. J. Watson, Implicit Time-Integration Method for Simultaneous Solution of a Coupled Non-Linear System, 2010.

J. C. Wood, B. A. Surette, and I. Aitchison, Pellet Cladding Interaction/Evaluation of Lubrification by Graphite, J. Nucl. Mater, vol.88, 1980.
DOI : 10.1016/0022-3115(80)90388-8

S. Yagnik, Effect of hydrides on the mechanical properties of Zircaloy4, International Topical Meeting on Light Water Reactor Fuel Performance, pp.191-199, 2004.

R. Yang, Revised reactivity initiated accident acceptance criteria for high burn-up fuel, Topical Report on Reactivity Initiated Accident: Bases for RIA Fuel and Core Coolability Criteria, EPRI, 2003.

]. I. Zmijarevic, Structure and contents of the Apollo2 output file SAPHYB, Reference SERMA, pp.9-4818, 2009.

I. Zmijarevic, . /. Den, and . Rt, Generation of multi-parameter cross sections libraries by APOLLO3, pp.10-5059, 2010.