, Nucl. Sci. Techn, vol.42, p.474, 2010.
Tripoli4 -A three dimensional polykinetic particle transport Monte Carlo code, Proc. Int. Conf. on Supercomputing in Nuclear Applications, SNA2003, 2003. ,
The JEFF-3.1.1 Nuclear Data Library, JEFF Report, vol.22, 2009. ,
URL : https://hal.archives-ouvertes.fr/cea-02386210
The art of collecting experimental data internationally: EXFOR, CINDA and the NRDC network, Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2007, 2007. ,
Updated User's Guide for SAMMY, 2006. ,
, Nucl. Sci. Eng, vol.150, p.109, 2005.
Solid State Effects on Thermal Neutron Cross Sections and on Low Energy Resonances, Proc. Int. Conf. on Nuclear Data for Science and Technology, 1982. ,
, Nucl. Sci. Eng, vol.127, p.105, 1997.
Experimental validation of the DARWIN-2.3 package for fuel cycle applications, Proc. of the Topical Meeting on Advances in Reactor Physics, PHYSOR2012, 2012. ,
, J. Nucl. Sci. Tech, vol.49, p.132, 2012.
, Translated from Atomnaya Energiya, vol.38, p.29, 1975.
Oak Ridge National Laboratory Report No. ORNL-3085, 1961. ,
The total cross section and the fission cross section of 2 41Am in the resonance region, resonance parameters, Proc. of Nuclear Data conference, 1975. ,
Validation of Actinide Nuclear Data for LWR applications, JEFF document JEFFDOC-1502, 2013. ,
, Nucl. Sci. Eng
, Nucl. Sci. Eng, vol.144, p.47, 2003.
Analysis of the MISTRAL experiment on LWR Reactivity Temperature Coefficient, Proc. of the Topical Meeting on Advances in Reactor Physics to Power the Nuclear Renaissance, PHYSOR2010, 2010. ,
, Nucl. Data Sheets, vol.113, p.2935, 2012.
Atlas of Neutron Resonances, vol.5, 2006. ,
Co-ordinated Evaluation of Plutonium-239 in the Resonance Region, WPEC Report, vol.34, 2014. ,
239 Pu resonance evaluation for thermal benchmark system calculations, Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2013, 2013. ,
JEFF-3.2T3 benchmarking -Criticality experiments to full reactor calculations, JEFF document JEFFDOC-1583, 2014. ,
URL : https://hal.archives-ouvertes.fr/cea-02386210
, Processing and benchmarking of the JEFF32T4 (JEFF-3.2) library, 2014.
Pu Prompt Fission Neutron Spectra Impact on a Set of Criticality and Experimental Reactors Benchmarks, Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2013, 2013. ,
, Eur. Phys. J. Plus, vol.128, p.86, 2013.
, Phys. Rev. C
, Phys. Rev. C, vol.81, p.64604, 2010.
Undermoderated PWR neutronic qualification through the ERASME experiment, Proc. of the Topical Meeting on Advances in Reactor Physics, 1987. ,
EPICURE : an experimental program devoted to the validation of the calculational schemes for plutonium recycling in PWRs, Proc. of the Int. Conf. on the Physics of Reactors : Operation Design and Computation, 1990. ,
, Nucl. Sci. Eng, vol.121, p.32, 1995.
MISTRAL: an experimental program in the EOLE facility devoted to 100% MOX core physics, Proc. Int. Conf. on Physics of Reactors, PHYSOR1996, 1996. ,
Core Physics experiment of 100% MOX core MISTRAL, Proc. Int. Conf. on Future Nuclear Systems, 1997. ,
First validation of neutronic lattice parameters of over moderated 100% MOX fuelled PWR cores on the basis of the MISTRAL experiment, Proc. Int. Conf. on the Physics of Nuclear Science and Technology: future Nuclear Systems, 1998. ,
MISTRAL-4 : an experimental mockup in the EOLE facility devoted to high moderation 100% MOX core Physics, Proc. Int. Conf on the Future Nuclear Systems, GLOBAL'99, 1999. ,
Analysis of MISTRAL and EPICURE experiments with SRAC and MVP code systems, Proc. Int. Conf. Physics of Reactor Operation, Design and Computation, PHYSOR2000, 2000. ,
Analysis of High Moderation PWR MOX Core MISTRAL-4 with SRAC and MVP, Proc. Int. Conf. on Nuclear Data for Science and Technology, 2001. ,
Analysis of MISTRAL Experiments with JENDL-3.2, Proc. Int. Conf. on Nuclear Data for Science and Technology, 2001. ,
Full MOX recycling in ALWR : Lessons Drawn through the MISTRAL Program, Proc. Int. Conf. PHYSOR2002, Seoul, Korea, 2002. ,
Analysis of the MISTRAL experiment with APOLLO2 qualification of neutronic parameters of UOX and MOX cores, Proc. Int. Conf. PHYSOR2002, Seoul, Korea, 2002. ,
Monte Carlo modeling of MISTRAL-4 100% MOX 17 × 17 ALWR mock-up cores using TRIPOLI-4.6, Proc. of the 2 nd Int. Conf. on Physics and Technology of Reactors and Applications, 2011. ,
BASALA: Advanced BWR MOX core physics experiments, Proc. of Int. Conf. on Advances in Reactor Physics and Mathematics, PHYSOR2000, 2000. ,
BWR MOX Core Physics Experiments and Preliminary Analysis, Proc. of the ANS Topical Meeting on Reactor Physics, PHYSOR2002, 2002. ,
FUBILA: core physics experimental program aimed at validation of core analysis method for high burn up BWR full MOX cores, Proc. Int. Conf. GLOBAL'05, 2005. ,
Experimental results and analysis of core physics experiments, FUBILA, for high burn-up BWR full MOX cores, Proc. of the ANS Topical Meeting on Reactor Physics, PHYSOR2006, 2006. ,
, J. Nucl. Sci. Tech, vol.47, p.1, 2010.
12 years of Franco-Japanese instrumental program in EOLE for the validation of 100% MOX recycling in ALWRS, Proc. of the ANS Topical Meeting on Reactor Physics, PHYSOR2014, 2014. ,
MVP/GMVP II: general purpose Monte Carlo codes fro neutron and photon transport calculations based on continuous energy and multigroup methods, 2005. ,
Optimisation de lapproche de representativite et de transposition pour la conception neutronique de programmes experimentaux dans les maquettes critiques, 2013. ,
URL : https://hal.archives-ouvertes.fr/tel-00979526
High-order discrete ordinate transport in non-confirming 2D cartesian meshes, Proc. Int. Conf. on Advances in Mathematics, Computational Methods, and Reactor Physics, 2009. ,
, Nucl. Sci. Eng, vol.167, p.209, 2011.
Estimation of multi-group cross section covariances, Proc. of the ANS Topical Meeting on Reactor Physics, PHYSOR2012, 2012. ,
Validation of the new code package APOLLO2.8 for accurate PWR calculations, Proc. Int. Conf. on Mathematics and Computation, M&C2013, 2013. ,
, Ann. Nucl. Ener, vol.35, p.2259, 2008.
, Nucl. Sci. Eng, vol.160, p.108, 2008.