A renaissance in fast reactor research and development and the rapid development of
computing technologies have encouraged improvements in fast reactor modeling and …

In this article, we formulate and implement an a priori Reduced-Order Model (ROM) of
neutron transport separated in energy by Proper Generalized Decomposition (PGD) …

High accuracy neutronic simulations are required for the development of Generation-IV
sodium cooled fast reactors (SFR). This paper therefore focuses on the development and …

Abstract Design of modern sodium fast reactors such as the French SFR project ASTRID are
axially heterogeneous in order to maximize neutron leakage and therefore improve their …

Fast resolution of the Boltzmann transport equation over a nuclear reactor core presupposes
the definition of homogenized and energy-collapsed cross sections. In modern sodium fast …

The accuracy of fast reactor core calculation is usually determined by the accuracy of self-
shielded few-group cross sections. To further improve the accuracy of cross section …

The development of fast reactors with complex designs and operation status requires more
accurate and effective simulation. The Monte-Carlo method can generate multi-group cross …

Computational accuracy and resource consumption are two sides of the mesh-based
neutron transport calculation, whose balance is a common concern in engineering …

In the past few years, developments in the APOLLO3® deterministic code have mainly been
devoted to Fast Reactor applications. In this paper, we investigate the possibility of using …

The design and safety assessment of nuclear reactors rely on a combination of calculations
performed by several simulation packages, each dedicated to modeling a specific ensemble …