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An alternative implementation of the dierential operator (Taylor series) perturbation method for Monte Carlo criticality problems, Nuclear Science and Engineering, vol.142, pp.327-341, 2002. ,
On the accuracy of the dierential operator Monte Carlo perturbation method for eigenvalue problems, Transactions of the American Nuclear Society, vol.101, pp.460-462, 2009. ,
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On using correlated sampling to simulate small changes in system response by MCNP, Annals of Nuclear Energy, vol.37, pp.34-42, 2010. ,
Impact of Perturbed Fission Source on the Effective Multiplication Factor in Monte Carlo Perturbation Calculations, Journal of Nuclear Science and Technology, vol.118, issue.9, pp.428-441, 2005. ,
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Enhanced correlated sampling by source biasing for pin diversion analysis, Transactions of the American Nuclear Society, vol.102, pp.220-221, 2010. ,
Monte Carlo method for geometrical perturbation and its application to the pulsed fast reactor, Nuclear Science and Engineering, vol.41, pp.259-270, 1970. ,
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Unbiased minimum variance estimator of a matrix exponential function. Application to Boltzmann, Bateman coupled equations solving, International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics, 2009. ,
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Error propagation in Monte Carlo burn-up calculations, International Conference on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications, 2005. ,
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Error propagation in Monte Carlo depletion analysis, Transactions of the American Nuclear Society, vol.96, pp.582-584, 2007. ,
Uncertainty propagation in Monte Carlo depletion analysis, International Conference on the Physics of Reactors, 2008. ,
Uncertainty propagation in Monte Carlo depletion analysis, Nuclear Science and Engineering, vol.167, pp.196-208, 2011. ,
Estimation of Error Propagation in Monte-Carlo Burnup Calculations, Journal of Nuclear Science and Technology, vol.62, issue.9, pp.738-745, 1999. ,
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Effect of error propagation of nuclide number densities on Monte Carlo burn-up calculations, Annals of Nuclear Energy, vol.33, issue.17-18, pp.1424-1436, 2006. ,
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Handbook of mathematical functions with formulas, graphs, and mathematical tables, 1972. ,
ROOT -A C++ framework for petabyte data storage, statistical analysis and visualization, 2009. ,
Monte Carlo technique for local perturbation in multiplying systems, Proceedings of the NEACRT meeting of a Monte Carlo study group, ANL-75-2, pp.261-280, 1974. ,
Systematic Uncertainty Due to Statistics in Monte Carlo Burnup Codes: Application to a Simple Benchmark with TRIPOLI-4-D, Progress in Nuclear Science and Technology, pp.879-885, 2011. ,
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ROOT ??? An object oriented data analysis framework, Proceedings AIHENP'96 Workshop, 1997. ,
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Études d'eets diérentiels par la méthode de Monte Carlo dans le cadre de l'équation du transport. Applications aux calculs de protection et de neutronique, Thèse de doctorat, 1982. ,
Automatisation de méthodes de réduction de variance pour la résolution de l'équation de transport, Thèse de doctorat, Ecole Nationale des Ponts et Chaussées, 2000. ,
Monte Carlo burnup code acceleration with the correlated sampling method. Preliminary test on an UOX cell with TRIPOLI-4, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, 2013. ,
Depletion calculations based on perturbations Application to the study of a REP-like assembly at beginning of cycle with TRIPOLI-4, Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA + MC 2013), La Cité des Sciences et de l'Industrie, 2013. ,
TRIPOLI-4 : A 3D continuous-energy Monte Carlo transport code, First International Conference on Physics and Technology of Reactors and Applications, 2007. ,
Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors, Nuclear Science and Engineering, vol.162, issue.3, pp.307-311, 2009. ,
DOI : 10.13182/NSE08-69TN
An overview on the Monte Carlo particle transport code TRIPOLI-4, Transactions of the American Nuclear Society, vol.97, pp.694-695 ,
Unbiased minimum variance estimator of a matrix exponential function. Application to Boltzmann, Bateman coupled equations solving, International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics, 2009. ,
Biases and Statistical Errors in Monte Carlo Burnup Calculations: An Unbiased Stochastic Scheme to Solve Boltzmann/Bateman Coupled Equations, Nuclear Science and Engineering, vol.167, issue.2, pp.165-170, 2011. ,
DOI : 10.13182/NSE09-100
An alternative implementation of the dierential operator (Taylor series) perturbation method for Monte Carlo criticality problems, Nuclear Science and Engineering, vol.142, pp.327-341, 2002. ,
On the accuracy of the dierential operator Monte Carlo perturbation method for eigenvalue problems, Transactions of the American Nuclear Society, vol.101, pp.460-462, 2009. ,
Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations, Annals of Nuclear Energy, vol.35, issue.4, pp.714-730, 2008. ,
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Monte Carlo perturbation theory in neutron transport calculations, Thèse de doctorat, 1980. ,
Cross-section adjustment with Monte Carlo sensitivities : application to the Winfrit iron benchmark, Nuclear Science and Engineering, vol.81, pp.423-431, 1982. ,
On using correlated sampling to simulate small changes in system response by MCNP, Annals of Nuclear Energy, vol.37, issue.1, pp.34-42, 2010. ,
DOI : 10.1016/j.anucene.2009.10.006
Uncertainty propagation in Monte Carlo burn-up calculations -State of the art report, rapport technique, p.8, 2008. ,
Method of estimating the sensitivity of a calculated nuclide vector to deviations in initial data, rapport technique, IAEA report INDC, p.418, 1998. ,
Error propagation in Monte Carlo burn-up calculations, International Conference on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications, 2005. ,
Monte Carlo particle transport methods : neutron and photon calculations, 1991. ,
Radioprotection et ingénierie nucléaire, EDP Science, 2006. ,
Improvement of Monte Carlo Lattice Burnup Calculation Performance with the Correlated Sampling Method, Journal of Nuclear Science and Technology, vol.23, issue.2, pp.587-596, 2002. ,
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Multi-Assembly Analysis with an Advanced Correlated Sampling Method, Journal of Nuclear Science and Technology, vol.63, issue.10, pp.905-917, 2003. ,
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Impact of Perturbed Fission Source on the Effective Multiplication Factor in Monte Carlo Perturbation Calculations, Journal of Nuclear Science and Technology, vol.118, issue.9, pp.428-441, 2005. ,
DOI : 10.1080/18811248.1995.9731849
Calculation of effective delayed neutron fraction with Monte Carlo perturbation techniques, Annals of Nuclear Energy, vol.38, issue.2-3, pp.254-260, 2011. ,
DOI : 10.1016/j.anucene.2010.10.020
Improvement of Correlated Sampling Monte Carlo Methods for Reactivity Calculations, Journal of Nuclear Science and Technology, vol.1255, issue.6, pp.400-410, 1978. ,
DOI : 10.1080/18811248.1978.9735527
The doppler eect for a non-uniform temperature distribution in reactor fuel elements, rapport technique, WCAP-2048, 1962. ,
Inventaire des techniques de biaisage dans les codes de transport de particules par la méthode Monte Carlo, rapport technique, 2009. ,
Précis de neutronique, Science, 2003. ,
Generalized Monte Carlo perturbation algorithms for correlated sampling and a second-order Taylor series approach, Annals of Nuclear Energy, vol.11, issue.9, pp.455-476, 1984. ,
DOI : 10.1016/0306-4549(84)90064-1
Stochastic perturbation analysis applied to neutral particle transport Advances in Nuclear Science and Technology, pp.69-140, 2002. ,
Nuclear data uncertainty propagation: Perturbation vs. Monte Carlo, Annals of Nuclear Energy, vol.38, issue.5, pp.942-952, 2011. ,
DOI : 10.1016/j.anucene.2011.01.026
Error propagation in Monte Carlo depletion analysis, Transactions of the American Nuclear Society, vol.96, pp.582-584, 2007. ,
Uncertainty propagation in Monte Carlo depletion analysis, International Conference on the Physics of Reactors, 2008. ,
Uncertainty propagation in Monte Carlo depletion analysis, Nuclear Science and Engineering, vol.167, pp.196-208, 2011. ,
Enhanced correlated sampling by source biasing for pin diversion analysis, Transactions of the American Nuclear Society, vol.102, pp.220-221, 2010. ,
Monte Carlo method for geometrical perturbation and its application to the pulsed fast reactor, Nuclear Science and Engineering, vol.41, pp.259-270, 1970. ,
Estimation of Error Propagation in Monte-Carlo Burnup Calculations, Journal of Nuclear Science and Technology, vol.62, issue.9, pp.738-745, 1999. ,
DOI : 10.1080/18811248.1991.9731356
TIMOC : a general purpose Monte Carlo code for stationary and time dependent neutron transport, 1970. ,
Effect of error propagation of nuclide number densities on Monte Carlo burn-up calculations, Annals of Nuclear Energy, vol.33, issue.17-18, pp.1424-1436, 2006. ,
DOI : 10.1016/j.anucene.2006.09.010
Monte Carlo technique for local perturbation in multiplying systems, Proceedings of the Conference on the Application of Computing Methods to Reactor Problems, ANL-705 0, pp.557-579, 1965. ,