Densités du caloporteur en sortie par assemblage (kg/m 3 ) 12465.5 12465 ,
Rayon interne de la pastille combustible ) ; // Cas d'une pastille annulaire Canal_1->SetCladRadius(Rayon de la gaine) ,
MCNP Utility for Reactor Evolution. user guide -version 1.0. report lpsc 0912, pp.9-10, 2009. ,
MCNP Utility for Reactor Evolution, description of the methods, first applications and results, ENC proceedings Versailles France, 2005. ,
MCNP ? a general Monte Carlo N-Particle transport code, version 5, 2003. ,
Résolution de l'´ equation de transport dans le code CRONOS, 1994. ,
The ERANOS code ans data system for fast reactor neutronic analyses. PHYSOR, 2002. ,
Nodal neutron kinetics code for LWR analysis, 1998. ,
WP-1-Report : Neutronics/thermal-hydraulics coupling in LWR technology, data requirements and databases needed for transient simulations and qualifications (database), 2004. ,
Neutronics/thermal-hydraulics coupling in LWR technology : State-of-art report (REAC-SOAR) ,
Neutronics/thermal-hydraulics coupling in LWR technology, achievements and recommendations report (finares), 2004. ,
Completion report for the coupled TRACS-M/PARCS code, university of purdue ,
Coupling of the thermo-hydraulic code ATHLET with the neutron kinetic core model DYN3D, Proc. International Conf. on Mathematics and Computation, Reactor Physics and Environmental Analyses ,
The thermal hydraulic code ATHLET for Analysis of PWR and BWR Systems, Proceedings Fourth International Topical Meeting on Nuclear Reactor Thermal hydraulics, pp.1234-1239, 1989. ,
Manuel des procédures de la version 2.7. CEA/SERMA, pp.4-3431, 2004. ,
APOLLO 2.5 : notice theorique, pp.99-2719, 2002. ,
Physics documentation of ERANOS and The ECCO cell code, Rapport Technique RT, pp.97-98 ,
A user guide for DRAGON 3.05D, 2007. ,
two-and three-dimensional discrete ordinates transport, version 2.7.3, ORNL RSICC, 1993. ,
DIAMANT-2 -continuous four-point triangular mesh difference schemes for the multigroup neutron transport equation, 1979. ,
Notice d'utilisation du code TRIPOLI 4, version 4 ,
Computation of a BWR Turbine Trip with CATHARE-CRONOS2-FLICA4 coupled codes, Nuclear Science and Engineering, vol.148, pp.235-246, 2004. ,
COBRA-EN an upgraded version of the COBRA-3C/MIT code for thermal-hydraulic transient analysis of light water reactor fuel assemblies and cores, ENEL-CRTN compartimento di Milano, 1999. ,
Design analysis of core assemblies for supercritical pressure condition, Nuclear Engineering and Design, vol.223, pp.279-294, 2003. ,
vipre-01 : a thermal-hydraulic analysis code for reactor cores, p.2511, 1983. ,
Table of isotopes, 1996. ,
Sodium cooled fast reactors : void coefficient and waste minimization. neutronics studies using MURE, 2009. ,
URL : https://hal.archives-ouvertes.fr/in2p3-00422482
First validation of the new continuous energy version of the MORET5 Monte Carlo code, 2008. ,
Convective heat transfer in liquid metals. Engineering division -Argonne National Laboratory ,
Réacteurs a neutrons rapides refroidis au sodium, 2005. ,
RéacteursRéacteursà eau sous pression, p.3100 ,
Le caloporteur sodium, 2004. ,
Thermodynamic and transport properties of sodium liquid and vapour. Reactor engineering division, chemical technology division -Argonne National Laboratory, 1995. ,
Le combustible nucléaire des réacteurs a eau sous pression et des réacteursréacteursà neutrons rapides -conception et comportement, CEA Eyrolles, 1996. ,
PWR MOX/UO2 core transient benchmark, final report, 2007. ,
Thermohydraulique des réacteursréacteursà eau sous pression, p.3050 ,
Mémento des pertes de charges. Direction desétudesdesétudes et recherche d'EDF, 1986. ,
ENDF2ACE user guide ,
Thermal scattering data and critically safety, International conference on the physics of reactors, 2008. ,
Monte Carlo -advances and challenges. workshop presentation at the 2008 ANS reactor physics division topical meeting, 2008. ,
Stationarity diagnostics using shannon entropy in Monte Carlo critically calculations i : F test, American nuclear society 2003 winter meeting, number LA-UR-03-3949, 2003. ,
Time Series Analysis of Monte Carlo Fission Sources - I: Dominance Ratio Computation, Nuclear Science and Engineering, vol.148, issue.3 ,
DOI : 10.13182/NSE03-95
Informatics approach to stationarity diagnostics of the Monte Carlo fission source distribution, American Nuclear Society 2003 winter meeting, pp.2-3783, 2003. ,
Coupled TORT-TD/CTF capability for high fidelity LWR core calculations, 2009. ,
Etude du potentiel de concepts innovants de réacteurs a neutrons rapides (RNR) vis-a-vis des exigences du développement durable, 2008. ,
Evaluation of reactor kinetic parameters without the need for perturbation codes, International RERTR meeting, 1997. ,
Monte Carlo calculation of the effective neutron generation time, Annals of Nuclear Energy, vol.33, issue.10, pp.911-916, 2006. ,
DOI : 10.1016/j.anucene.2006.05.001
Some preliminary calculations using the file gunall provided by SCK-CEN, 2009. ,
Calculation of the importance-weighted neutron generation time using MCNIC method, Annals of Nuclear Energy, vol.35, issue.8, pp.1397-1402, 2008. ,
DOI : 10.1016/j.anucene.2008.01.018
Study of the PWR REA pulse width for realistic UO2 and MOX core designs using 3D kinetics methods, Annals of Nuclear Energy, vol.36, issue.8, pp.1170-1183, 2009. ,
DOI : 10.1016/j.anucene.2009.04.007
Delayed neutron data for fast reactor analysis, Nuclear Science Engeneering, vol.50, p.208, 1973. ,
Calculating the Effective Delayed Neutron Fraction with Monte Carlo, Nuclear Science and Engineering, vol.152, issue.2, pp.142-148, 2006. ,
DOI : 10.13182/NSE03-107
Dynamics of nuclear reactors. American nuclear society, 1993. ,
DOI : 10.1063/1.3071101
Nuclear reactor dynamics. American nuclear society, 1985. ,
Fast breeder reactors. American nuclear society, 1981. ,
Physique des réacteurs nucléaires. Number ISBN 2-7061-0508-9, 1993. ,
Power series solution method for solving point kinetics equations with lumped model temperature and feedback, Annals of Nuclear Energy, vol.36, issue.2, pp.246-250, 2009. ,
DOI : 10.1016/j.anucene.2008.11.005