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

The work described in this thesis deals with the computational methods and algorithms used
in burnup calculations, which model changes in the composition of nuclear fuel under …

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 …

In general, spatial homogenization, energy group condensation, and angular approximation
are all included in the homogenization process. For the traditional pressurized water reactor …

We present recent improvements in assembly-level calculations for reactor analysis,
including modifications that support core-level analysis by quasi-diffusion. Our main focus is …

This paper introduces the albedo-corrected parameterized equivalence constants (APEC)
method, a new method for correcting the homogenized two-group cross sections of the …

SP 3 based pin-by-pin calculation has been proven to be efficient in improving the accuracy
of PWR cores with a strong heterogeneity. In this work, it is renamed “fine-mesh transport …

Abstract The Albedo-corrected Parameterized Equivalence Constants (APEC) method, a
new leakage correction method for two-group nodal analysis of light water reactors, has …

The pin-by-pin calculation method based on pin cell homogenization has become one of the
most interesting neutronics calculation methods since it can directly give the detailed pin cell …

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