Open Access
| Numéro |
EPJ Web Conf.
Volume 153, 2017
ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
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|---|---|---|
| Numéro d'article | 06007 | |
| Nombre de pages | 6 | |
| Section | 6. Calculation Methods Monte Carlo & Deterministic | |
| DOI | https://doi.org/10.1051/epjconf/201715306007 | |
| Publié en ligne | 25 septembre 2017 | |
- Brun, E., Damian, F., Diop, C.M., Dumonteil, E., Hugot, F.-X., Jouanne, C., Lee, Y.-K., Malvagi, F., Mazzolo, A., Petit, O., Trama, J.C., Visonneau, T., Zoia, A., “TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code”, Annals of Nuclear Energy, Volume 82, August 2015, Pages 151-160 [Google Scholar]
- Petit, O., Lee, Y.K., Diop, C., “Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations”, Progress in Nuclear Science and Technology Volume 4 (2014) pp. 408–412. [CrossRef] [Google Scholar]
- Zoia, A., Brun, E., Damian, F., Malvagi, F., “Monte Carlo methods for period calculations”, Annals of Nuclear Energy, Volume 75, 2015, Pages 627-634. [CrossRef] [Google Scholar]
- Truchet, G., Leconte, P., Santamarina, A., Brun, E., Damian, F., Zoia, A., ”Computing adjoint-weighted kinetics parameters in TRIPOLI-4® by the Iterated Fission Probability method”, Annals of Nuclear Energy, Volume 85, 2015, Pages 17-26. [Google Scholar]
- Damian, F., Brun, E., “ORPHEE research reactor: 3D core depletion calculation using Monte-Carlo code TRIPOLI-4®”, Annals of Nuclear Energy, Volume 82, 2015, Pages 203-216. [CrossRef] [Google Scholar]
- Brun, R., Rademakers, F., “ROOT - An Object Oriented Data Analysis Framework”, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Volume 389, 1997, Pages 81-86. See also http://root.cern.ch [CrossRef] [Google Scholar]
- Lee, Y.K, ”Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques”, ICRS-13 & RPSD2016, Paris, France, October 3-6, 2016 [Google Scholar]
- Riz, D., “Calculation and use of multigroup cross sections including electron-photon cascade for a 3D Monte Carlo neutron-gamma transport code. Comparisons with MCNP-4B,” in Proceedings of ANS PHYSOR, American Nuclear Society, 2000, CD-ROM. [Google Scholar]
- Verbeke, J. M., Petit, O., ”Stochastic Analog Neutron Transport with TRIPOLI-4 and FREYA: Bayesian Uncertainty Quantification for Neutron Multiplicity Counting”, Nuclear Science and Engineering, Vol. 183, Nb 2, June 2016, p. 214-228. [Google Scholar]
- Malouch, F., Lopez, F., Barbot, L., Fourmentel, D., “Calculation of neutron and gamma fluxes in support to the interpretation of measuring devices irradiated in the core periphery of the OSIRIS Material Testing Reactor”, ANIMMA2015, Lisbon Portugal, April, 20-24, 2015. [Google Scholar]
- Petit O., et al., ”FIFRELIN-TRIPOLI-4® coupling for Monte-Carlo simulations with a fission model. Application to shielding calculations”, ICRS-13 & RPSD2016, Paris, France, October 3-6, 2016. [Google Scholar]
- “Geant4 is a toolkit for the simulation of the passage of particles through matter”, http://geant4.cern.ch/ http://geant4.cern.ch/ [Google Scholar]
- Mancusi, D., Bringer, O., Monot, P., ”Progress on the TRIPOLI-4®-Geant4 coupling”, ICRS-13 & RPSD2016, Paris, France, October 3-6, 2016. [Google Scholar]
- Malouch, F, et al, “Recent developments in the TRIPOLI-4® Monte-Carlo code for fusion applications”, 29th Symposium on Fusion Technology (SOFT 2016), Prague, Czech Republic, 5-9 September 2016. [Google Scholar]
- Jaboulay, J.C., et al, “Rigorous-two-Step scheme of TRIPOLI-4® Monte Carlo code validation for shutdown dose rate calculation”, ICRS-13 & RDSD2016, Paris, France, October 3-6, 2016. [Google Scholar]
- Louvin, H., Diop C., Dumonteil, E., Lelièvre, T., Rousset, M., ”Adaptive Multilevel Splitting for Monte Carlo particle transport”, ICRS-13 & RPSD2016, Paris, France, October 3-6, 2016 [Google Scholar]