Numerous researchers have been unsuccessful in obtaining accurate LWR power
distributions using two-group nodal diffusion codes and neutronic data generated from …

This paper describes the methods used in the Serpent 2 Monte Carlo code for producing
homogenized group constants for nodal diffusion and other deterministic reactor simulator …

Nuclear reactors are stochastic systems, in which several parameters fluctuate even during
steady-state conditions. In addition, structural components like fuel assemblies, vibrate due …

Abstract At the Paul Scherrer Institut, the development of the SHARK-X methodology to
propagate nuclear data uncertainties in CASMO-5 2-D assembly depletion calculations …

Transport corrections are often used to account for the anisotropy in neutron scattering in
multi-group deterministic simulations of light water reactors. It remains an open question on …

This paper presents the theoretical foundations and the practical implementation of the
Fission Matrix Decomposition (FMD) method. The FMD method is a hybrid technique for the …

Nuclear reactors are inherently stochastic systems, in which neutronic and thermal-hydraulic
parameters fluctuate continuously even during steady-state conditions. In addition, structural …

Nodal diffusion codes have been successfully used for decades as a primary tool of
commercial power reactor design, safety calculations and plant cycle simulations. The large …

Nodal diffusion is currently the preferred neutronics model for industrial reactor core
calculations, which use few-group cross-section libraries generated via standard assembly …

This dissertation covers both experimental and numerical neutronics studies to evaluate the
adequacy of the Serpent/PARCS code sequence for modeling the steady-state and kinetics …