A myriad of nuclear reactor designs are currently being considered for next-generation
power production. These designs utilize unique geometries and materials and can rely on …

In this paper we describe some recent developments in the Method of Characteristics (MOC)
for three-dimensional (3D) extruded geometries in the nuclear reactor analysis code …

In recent years a solver based on the Method of Characteristics (MOC) allowing the
treatment of 3D extruded geometries has been developed inside the TDT code of APOLLO3 …

The new reactor analysis platform APOLLO3 R is under development at CEA and should
replace the current ERANOS code system for Fast Reactor studies. APOLLO3 R proposes …

The kinetic parameters of nuclear reactors describe the kinetic behavior of prompt and
delayed neutrons with respect to the fission, within a simplified representation of the time …

The reduction of the initial excess reactivity in fast reactor cores will enhance the inherent
safety level of the cores as it does reduce the impact of control rod withdrawal (CRW) …

CEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Some
innovative reactivity control systems are proposed such as utilization of different absorbers …

This thesis aims at improving the modelling of Pressurized Water Reactors (PWRs). Nuclear
reactors in general can be considered as multiphysic systems, as their accurate …

This paper presents a new breakdown methodology to estimate independently model
biases for each approximations of a given calculation scheme. This new methodology is set …

In this paper, we present recent advances on PWR core calculations schemes with the most
advanced features of the new deterministic neutronic transport code APOLLO3®. We focus …