. Rd-lawrence, Progress in nodal methods for the solution of the neutron diffusion and transport equations, Progress in Nuclear Energy, vol.17, issue.3, pp.271-301, 1986.

S. Kord and . Smith, Assembly homogenization techniques for light water reactor analysis, Progress in Nuclear Energy, vol.17, issue.3, pp.303-335, 1986.

A. Hebert, A consistent technique for the pin-by-pin homogenization of a pressurized water reactor assembly, Nuclear Science and Engineering, vol.113, issue.3, pp.227-238, 1993.

R. Sanchez, Assembly homogenization techniques for core calculations, Progress in Nuclear Energy, vol.51, issue.1, pp.14-31, 2009.

J. Dufek, Building the nodal nuclear data dependences in a many-dimensional state-variable space, Annals of Nuclear Energy, vol.38, issue.7, pp.1569-1577, 2011.

M. Onoue, T. Kawanishi, T. William-r-carlson, and . Morita, Application of MSHIM core control strategy for Westinghouse AP1000 nuclear power plant, GENES4/ANP2003, pp.15-18, 2003.

A. Grossetete, Le pilotage de l'EPR: mode T. Revue générale nucléaire, pp.37-41, 2007.

. Ch-lee, . Kim, C. O. Song, and . Park, Incorporation of a new spectral history correction method into local power reconstruction for nodal methods, Nuclear science and engineering, vol.124, issue.1, pp.160-166, 1996.

T. Iwamoto and M. Yamamoto, Advanced nodal methods of the few-group BWR core simulator NEREUS, Journal of nuclear science and technology, vol.36, issue.11, pp.996-1008, 1999.

D. M. Baturin and . Vygovskii, Taking account of the spectral history of fuel burnup during the preparation of the neutron-physical constants for VVER-1000 fuel assemblies, Atomic Energy, vol.90, issue.4, pp.267-272, 2001.

M. José and . Aragonés, Fundamentals of 3-D Neutron Kinetics and Current Status. THICKET-2008, 2008.

I. Bilodid and . Mittag, Use of the local Pu-239 concentration as an indicator of burnup spectral history in DYN3D, Annals of Nuclear Energy, vol.37, issue.9, pp.1208-1213, 2010.

E. Müller, L. Mayhue, and B. Zhang, Reactor physics methods development at Westinghouse, Proc. Int. Conf. Nuclear Energy for New, 2007.

P. Guimarães and E. Müller, Parameterization of two-group nodal cross section data for POLCA-T BWR transient applications, International Conference on Mathematics, Computational Methods, & Reactor Physics, 2009.

. Rd-mosteller, Impact of moderator history on physics parameters in pressurized water reactors, Nuclear Science and Engineering, vol.98, issue.2, pp.149-153, 1988.

A. Barreau, ;. Iid, . Assembly, . Pwruo, and . Oecd-nea, PWR-UO2 Assembly Study of Control Rod Effects on Spent Fuel Composition, 2006.

R. Sanchez and . Year, Nucl. Eng. and Technology, vol.42, pp.474-499, 2010.

F. Franceschini, B. Zhang, L. Mayhue, E. Müller, and P. Guimarães, Development of a control rod depletion methodology for the Westinghouse NEXUS system, Progress in Nuclear Energy, vol.68, pp.235-242, 2013.

P. E. Collins, N. Luciano, and G. I. Maldonado, Parametric study to capture the skin effect in PWR control rod depletion, Transaction of the American Nuclear Society, vol.109, pp.1327-1329, 2013.

. Venard, Contribution of the Experimental Validation of the French Criticality-Safety Package CRISTAL V1: APOLLO2 SN Route, 2003.

M. Coste-delclaux, Modélisation du phénomene d'autoprotection dans le code de transport multigroupe APOLLO2, 2006.

A. Hébert, Applied reactor physics. Presses inter Polytechnique, 2009.

P. D. Taylor and K. J. Rosman, Isotopic composition of the elements 1997, Pure and Applied Chemistry, vol.70, issue.1, pp.217-235, 1998.

P. Coppolani, La chaudière des réacteursà eau sous pression, 2012.

. Tj-pashos, Materials for Control of Water Cooled Power Reactors, Nuclear Technology, vol.4, issue.6, pp.395-398, 1968.