A MOC-based neutron kinetics model for noise analysis

A Gammicchia, S Santandrea, I Zmijarevic… - Annals of Nuclear …, 2020 - Elsevier
A 2-D noise model is implemented in the deterministic reactor code APOLLO3® to simulate
a periodic oscillation of a structural component. The Two/Three Dimensional Transport …

[HTML][HTML] Spectrum features of the eigenvalue formulations in neutron transport

N Abrate, S Dulla, P Ravetto, P Saracco - Annals of Nuclear Energy, 2024 - Elsevier
The steady state neutron transport equation can be studied resorting to different eigenvalue
formulations, useful to investigate the criticality state of a nuclear system. In this respect, the …

Spectral properties of dynamic processes in a nuclear reactor

AV Avvakumov, VF Strizhov, PN Vabishchevich… - Annals of Nuclear …, 2017 - Elsevier
As a rule, mathematical modeling of dynamic processes in nuclear reactors is conducted
using an approach that treats a neutron flux in the multigroup diffusion approximation. In this …

[HTML][HTML] Analysis of alpha modes in multigroup diffusion

R Sanchez, D Tomatis, I Zmijarevic, HG Joo - Nuclear Engineering and …, 2017 - Elsevier
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular
attention to the theoretical analysis of the model. Contrary to previous literature results, the …

State change modal method for numerical simulation of dynamic processes in a nuclear reactor

AV Avvakumov, VF Strizhov, PN Vabishchevich… - Progress in Nuclear …, 2018 - Elsevier
Modeling of dynamic processes in nuclear reactors is carried out, mainly, on the basis of the
multigroup diffusion approximation for the neutron flux. The basic model includes a …

Developing a Multiphysics Solver in APOLLO3 and Applications to Cross Section Homogenization

K Dugan - 2016 - theses.hal.science
Multiphysics coupling is becoming of large interest in the nuclear engineering and
computational science fields. The ability to obtain accurate solutions to realistic models is …

Cross section homogenization for transient calculations in a spatially heterogeneous geometry

K Dugan, R Sanchez, I Zmijarevic - Annals of Nuclear Energy, 2018 - Elsevier
The current norm in reactor accident simulation is to use homogenized cross sections that
are computed using a fundamental mode flux. It is shown however, that using such cross …