HTR-10 full core first criticality analysis with MCNP

Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

“…In other studies, the CFPs are distributed within the pebbles in a regular way, as well as the pebbles inside the core [5,13]. In the study by Abedi et al [14], the CFPs truncated by the boundary of fuel region inside fuel pebble were included in the study.…”

“…Several HTR-10 criticality analyses have been performed using codes of the MCNP family. In the study by Şeker and Ç olak [5], three different geometrical models were employed to study the effect of geometric details on the criticality calculations. Results were compared with diffusion theory-based calculations as well as with experimental data.…”

Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis

“…The SCALE/KENO-VI model served as a building block to represent the fuel zone in the three-dimensional (3-D) model of the HTR-10, as discussed later in this report. The MCNP model of the hexagonal fuel cell is similar to the model used by Seker and Colak [18]. A cross-sectional view of the MCNP5 model at half height of the cell is illustrated in Fig.…”

“…In the MCNP5 model, the fuel particles were modeled as used in Ref. 18, in a lattice structure that avoids the intersection of the particles with the pebble shell inner surface. The SCALE model accounts for double heterogeneity of the fuel through the method of processing the cross sections for the fuel zone.…”

“…18. The difference of five fuel pebbles, compared to the benchmark specifications [10], would correspond to a reduction of 0.05% in the total mass of uranium in the core.…”