P. A. Aarnio, Fluka user's guide, 1987.

M. Aufiero, A. Cammi, C. Fiorina, J. Leppänen, L. Luzzi et al., An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor, Journal of Nuclear Materials, vol.441, issue.1-3, pp.473-486, 2013.
DOI : 10.1016/j.jnucmat.2013.06.026

F. Bacha, J. Maillard, and J. Vergnes, Utilisation du code GEANT pour l'étude d'un réacteur de type hybride (Présentation et qualification du code), pp.95-122

F. Collége-de, Laboratoire de Physique Corpusculaire, pp.2-3, 1995.

G. P. Barros, C. Pereira, M. A. Veloso, A. L. Costa, and P. A. Reis, Neutron production evaluation from a ADS target utilizing the MCNPX 2.6.0 code, Brazilian Journal of Physics, vol.40, issue.4, pp.414-418, 2010.
DOI : 10.1590/S0103-97332010000400010

H. Bateman, Solution of a system of differential equations occurring in the theory of radio-active transformations, Math. Proc. Cambridge, vol.15, pp.423-427, 1910.

N. Doc, Benchmark on the Three-dimensional VENUS-2 MOX Core Measurements, Final Report, 2004.

C. D. Bowman, Nucl. Instr. and Meth. A, pp.320-336, 1992.

S. M. Bowman, M. D. Dehart, and L. M. Petrie, Integrated KENO Monte Carlo Transport for 3-D Depletion with SCALE The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Proc. of The Monte Carlo 2005 Topical Meeting, pp.on CD-ROM, 2005.

R. Brun, M. Hansroul, and J. C. Lassalle, GEANT3 User's Guide, CERN DD/EE/84-1. Computing and Networks Division, 1994.

C. Bungau, R. Barlow, A. Bungau, and R. Cywinski, Neutron Spallation Studies for an Accelerator Driven Subcritical Reactor, Proc. of 23 rd Particle Accelerator Conference PAC09, 2009.

J. F. Briesmeister, MCNP-A general Monte Carlo N-Particle Transport Code System, 2000.

O. Cabellos, N. García-herranz, C. J. Diez-de-la-obra, R. Alvarez-cascos, J. Sanz et al., Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code, Int. Conf. on Nuclear Data for Science and Technology, 2010.
DOI : 10.3938/jkps.59.1268

J. R. Cash and A. H. Karp, A variable order Runge-Kutta method for initial value problems with rapidly varying right-hand sides, ACM Transactions on Mathematical Software, vol.16, issue.3, pp.201-222, 1990.
DOI : 10.1145/79505.79507

N. Catsaros, B. Gaveau, M. Jaekel, J. Maillard, G. Maurel et al., Criticality qualification of a new Monte Carlo code for reactor core analysis, Annals of Nuclear Energy, vol.36, issue.11-12, pp.1689-1693, 2009.
DOI : 10.1016/j.anucene.2009.09.006

N. Catsaros, B. Gaveau, M. Jaekel, J. Maillard, G. Maurel et al., Building a dynamic code to simulate new reactor concepts, Nuclear Engineering and Design, vol.246, pp.41-48, 2012.
DOI : 10.1016/j.nucengdes.2011.10.015

N. Catsaros, B. Gaveau, M. Jaekel, A. Jejcic, J. Maillard et al., Investigating the breeding capabilities of hybrid soliton reactors, Nuclear Engineering and Design, vol.261, pp.251-259, 2013.
DOI : 10.1016/j.nucengdes.2013.04.022

J. Cetnar, A method of transmutation trajectories analysis in accelerator driven system Proceedings of the IAEA Technical Committee Meeting on Feasibility and Motivation for Hybrid Concepts for Nuclear Energy Generation and Transmutation, IAEA TC-903, pp.419-428, 1999.

J. Cetnar, W. Gudowski, and J. Wallenius, User Manual for Monte Carlo Continuous Energy Burnup (MCB) Code ? Version 1C, 2002.

J. Cetnar, General solution of Bateman equations for nuclear transmutations, Annals of Nuclear Energy, vol.33, issue.7, pp.640-645, 2006.
DOI : 10.1016/j.anucene.2006.02.004

A. G. Croff, A User's Manual for the ORIGEN2 Computer Code, p.7175, 1980.
DOI : 10.2172/5285077

A. G. Croff and . Origen-, ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials, Nuclear Technology, vol.39, issue.8, pp.335-352, 1983.
DOI : 10.13182/NT83-1

H. T. Dat, Mise au point de la bibliothèque physique et développement du système PEPABAC (PROGICIEL FAKIR) à l

C. Thèse-du-doctorat, . Saclay, and C. Note, , 1996.

J. David, C. Varignon, F. Borne, A. Boudard, F. Brochard et al.,

E. Martinez, S. Ménard, G. Milleret, Y. Patin, E. Petitbon et al., Spallation Neutron Production on Thick Target at SATURNE, Proc. of the Workshop on Nuclear Data for the Transmutation of Nuclear Waste, GSI-Darmstadt, 2003.

M. D. Dehart, M. C. Brady, and C. V. Parks, OECD/NEA, Burnup Credit Calcunational Criticality Benchmark Phase I-B Results, NEA/NSC/DOC(96)-06, p.6901, 1996.

N. , O. , N. /. Nsc, and . Doc, DICE: International Handbook of Evaluated Criticality Safety Benchmark Experiments, p.Edition, 2001.

J. Duderstadt and L. Hamilton, Nuclear Reactor Analysis, 1976.

E. Bakkari, B. Bardouni, T. Merroun, O. Younoussi, C. Boulaich et al., Validation of a new continuous Monte Carlo burnup code using a Mox fuel assembly, Nuclear Engineering and Design, vol.239, issue.10, pp.1828-1838, 2009.
DOI : 10.1016/j.nucengdes.2009.04.015

, Experiments for Nuclear-Chicago Student Training Reactor, Nuclear Chicago Corporation, 1959.

S. A. Feghhi and Z. Gholamzadeh, A MCNP simulation study of neutronic calculations of spallation targets, Nuclear Technology and Radiation Protection, vol.28, issue.2, pp.128-136, 2013.
DOI : 10.2298/NTRP1302128F

A. Ferrari and P. R. Sala, A New Model for Hadronic Interactions at Intermediate Energies for the FLUKA Code, Int. Conf. on Monte-Carlo Simulation in High- Energy and Nuclear Physics, 1993.

A. C. Fernandes, J. P. Santos, J. G. Marques, A. Kling, A. R. Ramos et al., Validation of the Monte Carlo model supporting core conversion of the Portuguese Research Reactor (RPI) for neutron fluence rate determinations, Annals of Nuclear Energy, vol.37, issue.9, pp.1139-1145, 2010.
DOI : 10.1016/j.anucene.2010.05.004

E. A. Gomin and L. V. Maiorov, The MCU Monte Carlo Code for 3D Depletion Calculation, Proc. ?f International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses in Nuclear Applications, pp.997-1006, 1999.

J. M. Gomit, P. Cousinou, C. Diop, G. Fernandez-de-grado, F. Gantenbein et al.,

A. Grouiller, D. Marc, H. Mijuin, and . Toubon, CRISTAL V1: Criticality package for burn up credit calculations, Proc. of the 7th International conference on nuclear safety safety-Challenges in the pursuit of global nuclear criticality safety (ICNC2003), Report JAERI-CONF, 2003.

N. A. Hanan, A. P. Olson, R. B. Pond, and J. E. Matos, A Monte Carlo burnup code linking MCNP and REBUS, ANL-TD-CP-97492, also Proc. of the 21st RERTR Meeting, 1998.

A. Isotalo, Computational Methods for Burnup Calculations with Monte Carlo Neutronics, 2013.

Y. Kadi and F. Carminati, Simulation of Accelerator-Driven Systems Workshop on Hybrid Nuclear Systems for Energy Production, Utilisation of Actinides & Transmutation of Long-Lived Radioactive Waste, European Organization for Nuclear Research, 2001.

A. Krása, F. K?í?ek, V. Wagner, A. Kugler, V. Henzl et al.,

, AIP Conf. Proc, vol.769, p.1555, 2005.

F. K?í?ek, V. Wagner, M. I. Krivopustov, A. J. , ?. P. Henzl et al., The study of spallation reactions, neutron production, and transport in a thick lead target and a uranium blanket during 1.5 GeV proton irradiation, Czechoslovak Journal of Physics, vol.257, issue.3, pp.243-252, 2006.
DOI : 10.1007/s10582-006-0085-7

J. R. Lamarsh and A. J. Baratta, Physics Today, vol.30, issue.6, 2001.
DOI : 10.1063/1.3037597

J. Leppänen, Development of a New Monte Carlo Rreactor Physics Code, 2009.

A. Leprince, J. David, D. Ene, and S. Leray, Reliability and use of INCL4.6-Abla07 spallation model in the frame of European Spallation Source target design, Progress in Nuclear Science and Technology, pp.491-495, 2014.
DOI : 10.15669/pnst.4.491

URL : https://hal.archives-ouvertes.fr/hal-01112732

E. E. Lewis and W. F. Miller, Computational Methods of Neutron Transport, pp.14-16, 1993.

H. Louis, E. Amin, M. Aziz, and I. Bashter, Studies on Production of Neutrons in the Spallation Reactions Using the Monte Carlo Code MCNPX, Nuclear Science and Engineering, vol.170, issue.6, pp.61-65, 2012.
DOI : 10.1016/S0168-583X(00)00259-7

M. Majerle, Monte Carlo methods in spallation experiments Report for the PhD State Exam, Department of Physics, Faculty of Nuclear Sciences and Physical Engineering, 2008.

V. Mantha, A. K. Mohanty, and P. Satyamurthy, Thermal hydraulic studies of spallation target for one-way coupled indian accelerator driven systems with low energy proton beam, Pramana, vol.335, issue.2, pp.355-363, 2007.
DOI : 10.1016/j.jnucmat.2004.07.007

J. E. Matos, J. G. Stevens, E. E. Feldman, J. A. Stillman, F. E. Dunn et al., Core conversion analyses for the Portuguese Research Reactor, Proceedings of 28 th International Meeting on Reduced Enrichment for Research and Test Reactors, 2006.

J. E. Matos, , 2005.

P. Meloni, G. Bandini, and M. Polidori, T/H and transient analyses to confirm EFIT preliminary design, Journal of Nuclear Materials, vol.376, issue.3, pp.405-408, 2008.
DOI : 10.1016/j.jnucmat.2008.02.081

, MCNPX User's Manual, 2002.

C. Mole and C. Van-loan, Nineteen Dubious Ways to Compute the Exponential of a Matrix, Twenty-Five Years Later, SIAM Review, vol.45, issue.1, pp.3-49, 2003.
DOI : 10.1137/S00361445024180

B. Na and N. Messaoudi, Benchmark on the Three-dimensional VENUS-2 MOX, 2003.

T. Nelson and B. G. Eddy, Foreign Research Reactor Uranium Supply Program: The Y- 12 National Security Complex Process In: Transactions of the Research Reactor Fuel Management Meeting RRFM-2010, 2010.

, Safety Evaluation Report related to the Evaluation of Low-Enriched Uranium Silicide-Aluminium Dispersion Fuel for use in Non- Power Reactors, Nuclear Regulatory Commission, 1988.

O. Nea,

M. Oden, A. Krása, M. Majerle, O. Svoboda, and V. Wagner, Monte-Carlo Simulations: FLUKA vs. MCNPX, AIP Conference Proceedings, p.219, 2007.
DOI : 10.1063/1.2825786

C. V. Parks, Overview of ORIGEN2 and ORIGEN-S: Capabilities and limitations, Proc. of the 3rd International Conference on High-Level Radioactive Waste Management, pp.57-63, 1992.

O. Petit, F. X. Hugot, Y. K. Lee, C. Jouanne, and A. Mazzolo, , 2008.

L. P. Piénkowski, W. Gawlikowicz, and D. Hilscher, FLUKA simulation for NESSI experiments, 2006.

R. E. Prael and H. Liechtenstein, User Guide to LCS:The LAHET Code System " Los Alamos National Laboratory informal report LA-UR, pp.89-3014, 1989.

, 101

M. Pusa and J. Leppänen, Computing the Matrix Exponential in Burnup Calculations, Nuclear Science and Engineering, vol.44, issue.2, pp.140-150, 2010.
DOI : 10.1137/05062590

M. Pusa and J. Leppänen, Efficient Implementation of CRAM method for Solving Burnup Equations, on CD-ROM, 2012.

C. H. Pyeon, Experimental Benchmarks of Neutronics on Solid Pb-Bi in Accelerator-Driven System with 100 MeV Protons at Kyoto University Critical Assembly, 2017.

G. Ren, W. Li, Y. Li, and M. Zeng, Simulation for Radiation Field caused by beam loss of C-ADS INJECTOR II, Proc. of International Beam Instrumentation Conference, pp.489-491, 2013.

P. K. Romano and B. Forget, The OpenMC Monte Carlo particle transport code, Annals of Nuclear Energy, vol.51, pp.274-81, 2013.
DOI : 10.1016/j.anucene.2012.06.040

URL : http://dspace.mit.edu/bitstream/1721.1/108130/1/annals-openmc.pdf

D. J. Rose and R. E. Tarjan, Algorithmic Aspects of Vertex Elimination on Directed Graph " s, SIAM, J. Comput, vol.5, pp.266-283, 1976.
DOI : 10.1137/0134014

M. W. Rosenthal, An Account of Oak Ridge National Laboratory's Thirteen Nuclear Reactors, pp.45-46, 2010.
DOI : 10.2172/970897

URL : https://www.osti.gov/servlets/purl/970897

C. Rubbia, Report CERN=AT=95?, vol.44, 1995.

M. Samson, J. P. Grouiller, J. Pavageau, and P. Marimbeau, Cesar: a simplified evolution code for reprocessing applications, Proc. of the 5th International Conference on recycling, conditioning and disposal (RECOD 98), 1998.

T. Sasa, K. Tsujimoto, T. Takizuka, and H. Takano, Code development for the design study of the OMEGA Program accelerator-driven transmutation systems " , Nuclear Instruments and Methods in Physics Research. Section A v, pp.495-504, 2001.

P. Savva, M. Varvayanni, A. C. Fernandes, J. G. Marques, and N. Catsaros, Comparing neutronics codes performance in analyzing a fresh-fuelled research reactor core, Annals of Nuclear Energy, vol.63, pp.731-741, 2014.
DOI : 10.1016/j.anucene.2013.08.036

D. She, Development of burnup methods and capabilities in Monte Carlo code RMC, Annals of Nuclear Energy, vol.51, pp.289-294, 2013.
DOI : 10.1016/j.anucene.2012.07.033

T. Sumner and S. Goluoglu, Verification of KENO V.A and KENO-VI Using Analytical Benchmarks, Proc. of the 8th International Conference on Nuclear Criticality Safety, pp.361-363, 2007.

B. J. Toppel, A User's Guide for the REBUS -3 Fuel-Cycle-Analysis Capability, 1983.
DOI : 10.2172/6068571

A. D. Vijaya and A. Kumar, The neutron spectrum of Am???Be neutron sources, Nuclear Instruments and Methods, vol.111, issue.3, pp.435-440, 1973.
DOI : 10.1016/0029-554X(73)90199-7

K. Wang, RMC ??? A Monte Carlo code for reactor core analysis, Annals of Nuclear Energy, vol.82, pp.121-129, 2015.
DOI : 10.1016/j.anucene.2014.08.048

Y. L. Zhang, X. C. Zhang, J. Qi, Z. Wu, and L. Yang, Study on the Parameters of the ADS Spallation Target, Journal of Physics: Conference Series, vol.420, p.12064, 2013.
DOI : 10.1088/1742-6596/420/1/012064

M. Zheng, W. Tian, H. Wei, D. Zhang, Y. Wu et al., Development of a MCNP???ORIGEN burn-up calculation code system and its accuracy assessment, Annals of Nuclear Energy, vol.63, pp.491-498, 2014.
DOI : 10.1016/j.anucene.2013.08.020

Z. Zhong, Y. Gohar, and A. Talamo, MCNPX and MCB Coupled Methodology for the Burnup Calculation of the KIPT Accelerator Driven Subcritical System, Proc. of " International Conference on Mathematics, 2009.

, LIST OF PUBLICATIONS

N. Catsaros, B. Gaveau, M. Jaekel, A. Jejcic, J. Maillard et al., Investigating the breeding capabilities of Hybrid Soliton Reactors Nuclear Energy for a New Europe, 20 th Int. Conf, 2011.

N. Catsaros, B. Gaveau, M. Jaekel, A. Jejcic, J. Maillard et al., Modeling and simulating a breeder hybrid soliton reactor Nuclear Energy for a New Europe, 21 st Int. Conf, 2012.

N. Catsaros, B. Gaveau, M. Jaekel, A. Jejcic, M. J. Maillard et al., Investigating the breeding capabilities of hybrid soliton reactors, Nuclear Engineering and Design, vol.261, pp.251-259, 2013.
DOI : 10.1016/j.nucengdes.2013.04.022

T. Xenofontos, G. Delipei, P. Savva, M. Varvayanni, N. Catsaros et al., Fluence Rate Benchmarking of the Stochastic Neutronic Code ANET Nuclear Energy for a New Europe, 24 th Int. Conf, 2014.

T. Xenofontos, P. Savva, M. Varvayanni, N. Chrysanthopoulou, N. Catsaros et al., Criticality Benchmarking of the Stochastic Neutronic Code ANET " , Int. Conf. " PHYSOR, 2014.

T. Xenofontos, G. Delipei, P. Savva, M. Varvayanni, J. Maillard et al., ANET reaction rates validation based on the Venus-2 MOX core benchmark analysis, 25 th Int. Conf. Nuclear Energy for New Europe '15, 2015.

T. Xenofontos, A. G. Mylonakis, P. Savva, M. Varvayanni, and N. Catsaros, The ANET code: from High Energy Physics to Stochastic Dynamic Neutronics with Thermal Hydraulic Feedback, Proc. of European Research Reactor Conference, 2016.

T. Xenofontos, G. Delipei, P. Savva, M. Varvayanni, J. Maillard et al., Testing the new stochastic neutronic code ANET in simulating safety important parameters, Annals of Nuclear Energy, vol.103, pp.85-96, 2017.
DOI : 10.1016/j.anucene.2017.01.012

, REFERENCES

J. R. Lamarsh and A. J. Baratta, Physics Today, vol.30, issue.6, 2001.
DOI : 10.1063/1.3037597

, Antonopoulos-Ntomis, Introduction to Nuclear Technology, 2005.

D. Leonidou, Introduction to Nuclear Technology, 2000.

S. E. Jensen and E. , Description of the Magnox Type Gas Cooled Reactor (MAGNOX), 1999.

, Heavy Water Reactors: Status and Projected Development, IAEA, 2002.

, UgUPvJynGjY Nikolay Tikhonov, WWER-1000 Reactor Simulator, 2011.

, Advanced Nuclear Power Reactors http://www.world-nuclear.org/info/Nuclear-Fuel- Cycle/Power-Reactors/Advanced-Nuclear-Power-Reactors

, Advanced Passive Pressurized Water Reactor, Status Report no, IAEA, issue.75, 2011.

A. Http, Status Report no. 93, 2011.

I. Vber-300, Status Report, issue.66, 2011.

, Official Site VBER-300 http

. Hitachi, The Hitachi ABWR plant general description, 2007.

, Candu Energy Inc., Enhanced CANDU, vol.6, 2012.

B. Atomic and R. Centre, Advanced Heavy Water Reactor, 2013.

A. and E. Tm-reactor, , p.131

, Status of Advanced Light Water Reactor Designs, IAEA, 2004.

I. and A. Tm, Status Report, issue.99, 2011.

A. The, A. Mhi, and . Tm-reactor, Generation III+ PWR, 2011.

, Advanced Power Reactor 1,400 MW e (APR1400), Status Report no, IAEA, issue.83, 2011.

. Hitachi-nuclear and . Energy, The Hitachi ESBWR Plant General Description, General Description Book, 2011.

, Advanced CANDU Reactor 1000 (ACR1000), Status Report no, IAEA, issue.69, 2011.

R. Roadmap, A. Developing, and . Technology, ANL-99, 1999.

, Accelerator-driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles, OECD-NEA Report, 2002.

F. Bacha, J. Maillard, and J. Vergnes, Utilisation du code GEANT pour l'étude d'un réacteur de type hybride (Présentation et qualification du code, pp.95-122

F. Collége-de, Laboratoire de Physique Corpusculaire, pp.2-3, 1995.

E. S. Bettis and R. C. Robertson, The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor, Nuclear Applications and Technology, vol.8, issue.2, p.190, 1970.
DOI : 10.13182/NT70-A28625

C. D. Bowman, Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol.320, issue.1-2, p.336, 1992.
DOI : 10.1016/0168-9002(92)90795-6

J. Bussac and P. Reuss, Traité de neutronique, 1985.

N. Catsaros, B. Gaveau, M. Jaekel, A. Jejcic, J. Maillard et al., Investigating the breeding capabilities of hybrid soliton reactors, Nuclear Engineering and Design, vol.261, pp.251-259, 2013.
DOI : 10.1016/j.nucengdes.2013.04.022

K. Furukawa, The combined system of accelerator molten salt breeder (AMSB) and molten salt converter reactor (MSCR), Japan?US Seminar on Thorium Fuel Reactors, 1982.

P. Kadak and C. Andrew, Lecture 4, Fuel Depletion & Related Effects Operational Reactor Safety 22.091/22.903, Hemisphere, as referenced by MIT. p. Table 6?1 Average Conversion or Breeding Ratios for Reference Reactor Systems, pp.91-99

M. Mizumoto, High intensity proton accelerator for nuclear waste transmutation, 16th International Linear Accelerator Conference LINAC-92, 1992.

H. Nifenecker, S. David, J. M. Loiseaux, and O. Meplan, Basics of accelerator driven subcritical reactors " , Nuclear Instruments and Methods in Physics Research A 463, pp.428-467, 2001.

D. Ridikas and W. Mittig, Neutron production and energy generation by energetic projectiles: protons or deuterons?, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol.418, issue.2-3, p.449, 1998.
DOI : 10.1016/S0168-9002(98)00897-3

URL : https://hal.archives-ouvertes.fr/in2p3-00021914

C. Rubbia, Report CERN=AT=95?, vol.44, 1995.

W. M. Stacey, Nuclear Reactor Physics, 2001.