Nuclear data and processing

Methods for core neutronics calculation

Figure 1 - Comparison of the effective capture cross section of the 238U (JEFF-3.1.1) with a flux representative of a sodium-cooled RNR (red curve) and that of a PWR (blue curve).

Figure 2 - Simplified library development scheme for Monte Carlo and deterministic transport codes

Figure 3 - &#34;Calculating the world&#039;s effective multiplication factor (from [4])

Figure 4 - Illustration of the convergence of keff as a function of the number of cycles and for different configurations of the initial (arbitrary) neutron source.

Figure 5 - Example of a histogram of keff obtained by Monte-Carlo simulation of the critical system shown in figure 3.

Figure 6 - Code TRIPOLI-4® – experience Gondola

Figure 7 - Principle of Boltzmann/Bateman coupling in TRIPOLI-4®

Figure 8 - Homogenization of a REP assembly per cell

Figure 9 - Illustration of the energy self-protection phenomenon

Figure 10 - Equivalence for a mixture of resonant cores

Figure 11 - Description of the horizontal section of the assembly

Figure 12 - Examples of geometries calculated with APOLLO2

Figure 13 - Examples of geometries processed with CRONOS2

Figure 14 - MINOS solver calculation for the Jules Horowitz reactor

Figure 15 - 3D heterogeneous SPN transport calculation with APOLLO3 for a pressurized water reactor

Figure 16 - 3D heterogeneous SN transport computation with APOLLO3 for a sodium-cooled RNR

Figure 17 - Flux distribution as a function of neutron energy in the Jules Horowitz reactor

Figure 18 - Typical power evolution during an RIA

Figure 19 - Typical evolution of the hot-spot factor during an RIA

Figure 20 - System, core and neutronics thermal-hydraulic coupling used to simulate the RTV accident

Figure 21 - Neutron calculation code validation stage

Figure 22 - Neutron calculation code form qualification stage

Figure 23 - Steps in the VVUQ process