For practical reactor core applications, low-order transport approximations such as SP3
have been shown to provide sufficient accuracy for both static and transient calculations with …

A high-order cross-section homogenization method based on boundary condition
perturbation theory is developed to improve the accuracy of nodal methods for coarse-mesh …

Three-dimensional deterministic core calculations are typically based on the classical two-
step calculation scheme. The sizable number of approximations introduced in this approach …

Three-dimensional deterministic core calculations are typically based on the classical two-
step approach, where the homogenized cross sections of an assembly type are …

AREVA has developed a new coupled neutronics/thermal-hydraulics code system,
ARCADIA®. It makes use of modern computing resources to enable more realistic reactor …

[en] There has been concern during the last several years that the advanced nodal methods
which have been developed for LWR cores initially fueled with Uranium do not provide the …

A hybrid nodal diffusion/simplified P 3 (SP 3) method was implemented within the framework
of a one-node coarse-mesh finite difference formulation. The one-node formulation enables …

Cross sections used in nodal calculations come from infinite medium flux homogenization.
Their dependencies from physical working conditions are solved through interpolation on …

In CANDU R reactor calculations, the lattice-cell cross sections are calculated with WIMS-
AECL, and the three-dimensional core neutron-flux and power distributions are calculated …

The classical two-step calculation scheme has been extensively used to perform three-
dimensional deterministic core calculations thanks to its fast results. On the other hand …