J. Leppänen, SERPENT: a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code, 2013.

J. Ho and . Park, Generation of few group diffusion theory constants by Monte Carlo code McCARD, Nuclear Science and Engineering, vol.172, issue.1, pp.66-77, 2012.

J. E. Hoogenboom, V. A. Khotylev, and J. M. Tholammakkil, Generation of multi-group cross sections and scattering matrices with the Monte Carlo code MCNP5, Joint International Topical Meeting on Mathematics & Computations and Supercomputing in Nuclear Applications. Monetery, USA, 2007.

S. C. Van-der-marck, J. C. Kuijper, and J. Oppe, In: Physor The Role of Reactor Physics toward a Sustainable Future, 2006.

L. Cai, P1 adaptation of TRIPOLI-4 code for the use of 3d realistic core multigroup cross section generation, Joint International Conference on Supercomputing in Nuclear Application and Monte Carlo, p.31, 2013.

S. Nam-zin-cho, J. Yun, and . Lee, Generation of homogenized nodal parameters by Monte Carlo method with non-zero leakage spectra in global-local iteration framework, Transactions of the American Nuclear Society, vol.101, pp.707-710, 2009.

T. Yamamoto, Monte carlo method with complex weights for neutron leakage-corrected calculations and anisotropic diffusion coefficient generations, Annals of Nuclear Energy, vol.50, pp.141-149, 2012.

T. Yamamoto, Improvements and new findings in Monte Carlo method with complexvalued weights for neutron leakage-corrected assembly calculations, Joint International Conference on Supercomputing in Nuclear Application and Monte Carlo, pp.27-31, 2013.

J. Both, A survey of TRIPOLI4, Int. Conf. on Radiation Shielding, 1994.

E. Brun, Overview of TRIPOLI4 version 7 Continuous-energy Monte Carlo Transport Code, 2011.

J. Both and Y. K. Lee, Computations of homogenised multigroup cross sections with the Monte Carlo code TRIPOLI4, In: SARATOGA JIC MM SNA. Saratoga Springs, 1997.

, NEA-1716 TRIPOLI-4 VERS. 8.1, 2013.

G. Rimpault, Algorithmic features of the ECCO cell code for treating heterogeneous fast reactor assemblies, Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analyses, 1995.

M. J. Grimstone, J. D. Tullett, and G. Rimpault, Accurate treatments of fast reactor fuel assembly heterogeneity with the ECCO cell code, Int. Conf. on the Physics of Reactors: Operation, Desing and Computation-PHYSOR 90, p.27, 1990.

N. Martin and A. Hébert, Adaptation of the B1 leakage model to Monte Carlo criticality calculations, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, 2011.

T. Sanda, A 1,000 MWe-Class Sodium-cooled MOX-Fueled FBR Homogeneous Core Mock-up Critical Experiment in the state of removal of one of eighteen half-inserted control rods, where enriched uranium is used with the shape of a sector

, THE JEFF-3.1.1 NUCLEAR DATA LIBRARY OECD/NEA 2009, 2009.

L. Gastaldo, High-order discrete ordinate transport in non-confirming 2d cartesian meshes, In: Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, 2009.

G. Truchet, Continuous-energy adjoint flux and perturbation calculation using the iterated fission probability method in Monte Carlo code TRIPOLI-4 and underlying applications, Joint International Conference on Supercomputing in Nuclear Application and Monte Carlo, p.31, 2013.

G. Rimpault, The ERANOS code and data system for fast reactor neutronic analyses, In: Int. Conf. PHYSOR. Seoul, 2002.
URL : https://hal.archives-ouvertes.fr/cea-02906396

J. M. Ruggieri, ERANOS 2.1: International code system for gen iv fast reactor analysis, Int. Conf. ICAPP'06, 2006.

G. Palmiotti, Optimized two-dimensional Sn transport(BISTRO), Nuclear Science and Engineering, vol.104, pp.26-33, 1990.