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 | 05008 | |
Nombre de pages | 8 | |
Section | 5. Fission Facilities, Fuel Cycle & Waste Management Facilities, Decommissioning | |
DOI | https://doi.org/10.1051/epjconf/201715305008 | |
Publié en ligne | 25 septembre 2017 |
- P. Ferdinand et al., “DISCOMS: DIstributed Sensing for COrium Monitoring and Safety”, CANSMART 2015: International Conference on Smart Materials and Structures - Vancouver, BC, Canada (2015) [Google Scholar]
- H. Panek “Qualification du systéme NEPTUNE — Ebauche d'une nouvelle chaine de calcul basée sur les codes APOLLO et Tortise”, Note CEA-N-2092, (1979) [Google Scholar]
- X-5 Monte Carlo Team, “MCNP - A general Monte Carlo n-particle transport code, version 5”, Los Alamos National Laboratory, (2005) [Google Scholar]
- M. Brovchenko et al., “Neutron-gamma flux and dose calculations for feasibility study of instrumentation implementation in the European Pressurized Reactor (EPR)”, submitted to ICRS-I 3 & RPSD-20I6 [Google Scholar]
- T. Goorley et al., “Initial MCNP6 Release Overview — MCNP6 version 1.0”, LA-UR-13-22934, (2013) [Google Scholar]
- A. Dubi et al., “General Statistical Model for Geometrical Splitting in Monte Carlo — parts I and II”, Transp. Theory Stat. Phys. 14 (2), 167-193 and 195-221 (1985) [CrossRef] [Google Scholar]
- K.W. Burn, “Optimizing Monte Carlo to multiple responses: the Direct Statistical Approach, 10 years on”, Nuclear Technology 175, 138–145 (2011) [CrossRef] [Google Scholar]