A characteristics formulation of the neutron transport equation in complicated geometries, Tech. rep., UK Atomic Energy Estabilishment, 1972. ,
Linear source approximation in CASMO5, p.2012 ,
The OpenMOC method of characteristics neutral particle transport code, Annals of Nuclear Energy, vol.68, pp.43-52, 2014. ,
DOI : 10.1016/j.anucene.2013.12.012
The cyclic characteristic method, Physics of Nuclear Science and Technology, 1998. ,
APOLLO2 YEAR 2010, Nuclear Engineering and Technology, vol.42, issue.5, pp.474-499, 2010. ,
DOI : 10.5516/NET.2010.42.5.474
Conception et développement d'un mailleurénergétiquemailleurénergétique adaptatif pour la génération des bibliotéques multigroupes des codes de transport, 2009. ,
Handbook of Mathematical Functions, American Journal of Physics, vol.34, issue.2, 1965. ,
DOI : 10.1119/1.1972842
Numerical methods for large eigenvalue problems, p.171, 2011. ,
DOI : 10.1137/1.9781611970739
Ray Effects in Discrete Ordinates Equations, Nuclear Science and Engineering, vol.32, issue.3, 1968. ,
DOI : 10.13182/NSE68-4
On the Construction of Galerkin Angular Quadratures, Nuclear Science and Engineering, vol.169, issue.2, pp.133-154, 2011. ,
DOI : 10.13182/NSE10-31
Derivation of new 3D dicrete ordinate equations, p.2012 ,
PROSPECTS IN DETERMINISTIC THREE-DIMENSIONAL WHOLE-CORE TRANSPORT CALCULATIONS, Nuclear Engineering and Technology, vol.44, issue.2, pp.113-150, 2012. ,
DOI : 10.5516/NET.01.2012.501
Validation of new sub-group algorithms for resonance self shielding in heterogeneous structures, in: Topical Meeting on Advances in Nuclear En-gineering Computation and Radiation Shielding, 1989. ,
Les tables de probabilite: application au traitement des sections efficaces pour la neutronique, CEA, 1986. ,
ENDF-6 data formats and procedures for the evaluated nuclear data file ENDF-VII, Cross Section Evaluation Working Group, 2005. ,
Subgroup method in the APOLLO3 selfshielding calculations, 2011. ,
Correction of multigroup cross sections for resolved resonance interference in mixed absorbers, Nuclear Science and Engineering, vol.83, pp.9-37, 1983. ,
Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code, Progress in Nuclear Energy, vol.48, issue.5, pp.456-466, 2006. ,
DOI : 10.1016/j.pnucene.2006.01.006
and Radial MOC Coupled Whole Core Transport Calculation, Journal of Nuclear Science and Technology, vol.48, issue.6, pp.1156-1171, 2007. ,
DOI : 10.1080/18811248.2007.9711359
Lathuilì ere, Micado: Parallel implementation of a 2D-1D iterative algorithm for the 3D neutron transport problem in prismatic geometries, p.2013 ,
Résolution de l'´ equation de transport par des méthodes nodales et des caractéristiques dans les domainesàdomainesà trois dimensions, 1998. ,
Domain-decomposition method for 2D and 3D transport calculations using hybrid MPI/OpenMP parallelism, p.2015 ,
MCCG3D -3D discrete-ordinates transport code for unstructured grid. state of the art and future development, Proceedings of Seminar " Neutronics-96, p.162, 1998. ,
A new characteristics algorithm for 3D transport calculations, Annals of Nuclear Energy, vol.30, issue.1, pp.1-16, 2003. ,
DOI : 10.1016/S0306-4549(02)00046-4
Overview of development and design of MPACT: Michigan parallel characteristics transport code, American Nuclear Society -ANS, p.2013 ,
A new three-dimensional method of characteristics for the neutron transport calculation, Annals of Nuclear Energy, vol.38, issue.2-3, pp.447-454, 2011. ,
DOI : 10.1016/j.anucene.2010.09.021
A method of characteristics solution to the oecd/nea 3D neutron transport benchmark problem, 2007. ,
Techniques de traçage pour la méthode des caractéristiques appliquéè a la résolution de l' ´ equation du transport des neutrons en domaines multi-dimensionnels, 2009. ,
Improvements and validation of the linear surface characteristics scheme, Annals of Nuclear Energy, vol.36, issue.1, pp.46-59, 2009. ,
DOI : 10.1016/j.anucene.2008.10.007
Extension of linear source MOC method to anisotropic scattering in CASMO5, p.2014 ,
Higher-order method of characteristic for 2-D unstructured meshes, 2009. ,
A robust arbitrarily high order transport method of the characteristic type for unstructured tetrahedral grids, 2009. ,
The linear source approximation in three dimension characteristics method, 2009. ,
Acceleration techniques for trajectory-based deterministic 3D transport solvers, Annals of Nuclear Energy, vol.30, issue.5, pp.567-583, 2003. ,
DOI : 10.1016/S0306-4549(02)00094-4
Effectiveness of a consistently formulated diffusion synthetic acceleration differencing approach, Nuclear Science and Engineering, vol.98, pp.226-243, 1988. ,
An algebraic collapsing acceleration in long characteristic transport theory, Proc. 11th Symp, p.162, 2001. ,
An improved algebraic collapsing acceleration with general boundary conditions for the characteristics method, Nuclear Science and Engineering, vol.156, pp.121-138, 2007. ,
A low order non linear transport acceleration scheme for the method of the characteristic, p.2014 ,
Analysis and improvements of the DPN acceleration technique for the method of characteristics in unstructured meshes, Annals of Nuclear Energy, vol.32, issue.2, pp.163-193, 2005. ,
DOI : 10.1016/j.anucene.2004.08.011
Acceleration techniques for the characteristic method in unstructured meshes, Annals of Nuclear Energy, vol.29, issue.4, pp.323-352, 2002. ,
DOI : 10.1016/S0306-4549(01)00049-4
Optimized tracking strategies for step MOC calculations in extruded 3D axial geometries, Annals of Nuclear Energy, vol.87 ,
DOI : 10.1016/j.anucene.2015.05.014
Treatment of Boundary Conditions in Trajectory-Based Deterministic Transport Methods, Nuclear Science and Engineering, vol.140, issue.1, pp.23-50, 2002. ,
DOI : 10.13182/NSE140-23
Improvements of the reactivity devices modeling for the advanced {CANDU} reactor, Annals of Nuclear Energy, vol.35, issue.5, pp.868-876, 2008. ,
Improvements in the long characteristics method and their efficiency for deep penetration calculations, Progress in Nuclear Energy, vol.39, issue.2, pp.223-242, 2001. ,
DOI : 10.1016/S0149-1970(01)00014-2
Tracking strategies in 3D axial geometries for a MOC solver, SNA + MC 2013, Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo ,
DOI : 10.1051/snamc/201402209
What every programmer should know about memory, 2007. ,
Analyse et développement d'un schéma de discrétisation numérique de l'´ equation du transport des neutrons en géométrie tridimensionelle, 2014. ,
Forget, Parallel performance results for the OpenMOC method of characteristic code on multi-core platforms, p.2014 ,
Development and parallelization of the three-dimensional characteristics solver MCI of DRAGON, 2002. ,
Coupled fine-group three-dimensional flux BIBLIOGRAPHY calculation and subgroups method for a fbr hexagonal assembly with the APOLLO3 ® core physics analysis code, p.2015 ,
Optimal polar angles and weights for the characteristics method, Trans. Am. Nucl. Soc, vol.172, p.73, 1995. ,
Derivation of Optimum Polar Angle Quadrature Set for the Method of Characteristics Based on Approximation Error for the Bickley Function, Journal of Nuclear Science and Technology, vol.40, issue.2, pp.129-136, 2007. ,
DOI : 10.1080/00207729308949510
Methods of numerical integration, 1975. ,
A method for numerical integration on an automatic computer, Numerische Mathematik, vol.9, issue.1, pp.197-205, 1960. ,
DOI : 10.1007/BF01386223
Is gauss quadrature better than Clenshaw-Curtis?, SIAM Rev, pp.67-87, 2008. ,
Numerical Recipes 3rd Edition: The Art of Scientific Computing, 2007. ,
A survey of TRIPOLI-4, Proceedings of the 8th International Conference on Radiation Shielding, 1994. ,
Angular quadrature formulas for step-MOC calculations in three-dimensional axial geometries, pp.3-2014 ,
Sodium-cooled fast reactors: the astrid plant project, 2011. ,
MINARET, a deterministic neutron transport solver for nuclear core calculations, M&C, Rio de Janeiro (BR), 2011. ,
URL : https://hal.archives-ouvertes.fr/cea-00545919
The ERANOS code and data system for fast reactor neutronic analyses, 2002. ,