Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a Gas-cooled Fast Reactor

Development of a 3D-Multigroup program to simulate anomalous diffusion phenomena in the nuclear reactors

“…In this sense we can cite the work of Reyes-Ramírez et al (2010), who show that the results of the infinite multiplication factor as a function of the irradiation time for heterogeneous and homogeneous configuration is similar. This result is revealing due that the consideration of the highly heterogeneous system may not be a sufficient condition in order to use the fractional model in a fast reactor.…”

Depletion calculations based on perturbations. Application to the study of a REP-like assembly at beginning of cycle with TRIPOLI-4®

“…To validate and qualify the performances of this method, it has been implemented in the depletion option of the TRIPOLI-4 Ò code (Reyes-Ramìrez et al, 2010;Brun and Dumonteil, 2012). This option couples TRIPOLI-4 Ò (Diop et al, 2006;Brun et al, 2011a) for the transport part and MENDEL (Bellier et al, 2012) for the depletion part -both codes being developed at CEA Saclay-through a C++ interface using the ROOT framework developed at CERN (Antcheva et al, 2009).…”

“…But with this procedure no confidence intervals are provided on isotopic inventories. To overcome this drawback, a new procedure was implemented in the TRIPOLI-4 Ò burnup card Dumonteil, 2010, 2012;Reyes-Ramìrez et al, 2010), which consists in simultaneously launching independent monoprocessed Monte-Carlo burnup simulations to compute statistical uncertainties on all tallies. In the following, we use this capability and all results will be provided with statistical uncertainties from 200 independent replica of the depletion.…”

NEUTRONIC PERFORMANCE OF (U, Pu)C FUEL IN A LATTICE OF GFR USING SCALE 6.0

“…In this work is used SCALE 6.0 (Standardized Computer Analysis for Licensing Evaluation -version 6.0) code to simulate the hexagonal fuel assembly from a typical GFR. The geometry and the isotopic composition of the components were based on previous studies [1,3]. The burn-up was performed using the TRITON-6 module.…”