Monte Carlo Codes for Neutron Buildup Factors

The point-kernel method is a widely used practical tool for gamma-ray shielding calculations. However, application of that neutron transport simulations very limited. accuracy the strongly depends on buildup factors in Buildup are usually obtained using appropriate computer codes, either based discrete ordinates or Monte Carlo approach. Since these codes put strong demands resources, they applied limited number configurations and an attempt made to use results formulate empirical expression estimation. Due high physical complexity through material it hard perform parameterisation order establish adequate formula. Existing formulas applicable narrow energy range few commonly materials, mostly monolayer configuration. Recently, new approach has been proposed determination gamma ray mono-layer, as well multi-layer covering wide range. regression model support vector machines learning technique, which theoretical background statistical theory. Development named required large experimental data by code. More than 7000 runs were required. likely require even more generate reasonable accuracy. Therefore, choice code important question. One take into account time input preparation running What also be considered possibility incorporated algorithm automated generation data. In this paper three analysed, namely SCALE4.4 package (SAS3 sequence), SCALE6.0 (MAVRIC MCNP5. Two simple setups point isotropic source spherical slab-like shield modelled, examined previously mentioned issues. comparison show each one potential factor generation. some aspects their utilization further analysis prior final selection.