APOLLO3® CEA/DEN deterministic multi-purpose code for reactor physics analysis

D Schneider, F Dolci, F Gabriel, JM Palau… - … –Unifying Theory and …, 2016 - cea.hal.science
APOLLO3® is a common project of CEA, AREVA and EDF for the development of a new
generation code system for core physics analysis providing improved accuracy, flexible …

SARAX: A new code for fast reactor analysis part I: Methods

Y Zheng, X Du, Z Xu, S Zhou, Y Liu, C Wan… - Nuclear Engineering and …, 2018 - Elsevier
A renaissance in fast reactor research and development and the rapid development of
computing technologies have encouraged improvements in fast reactor modeling and …

[HTML][HTML] APOLLO3 homogenization techniques for transport core calculations—application to the ASTRID CFV core

JF Vidal, P Archier, B Faure, V Jouault, JM Palau… - Nuclear Engineering …, 2017 - Elsevier
This paper presents a comparison of homogenization techniques implemented in the
APOLLO3 platform for transport core calculations: standard scalar flux weighting and new …

Neutronic calculation of an axially heterogeneous ASTRID fuel assembly with APOLLO3®: Analysis of biases and foreseen improvements

B Faure, P Archier, JF Vidal, JM Palau, L Buiron - Annals of Nuclear Energy, 2018 - Elsevier
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 …

Validation of the Newly Implemented 3D TDT-MOC Solver of APOLLO3 Code on a Whole 3D SFR Heterogeneous Assembly

P Archier, JM Palau, JF Vidal, S Santandrea… - … 2016-Unifying Theory …, 2016 - cea.hal.science
A three-dimensional (3D) axial capabilities have been recently implemented in the TDT-
MOC solver (Method of Characteristics solver), module of the French deterministic core …

[HTML][HTML] Numerical validation of the APOLLO3®-FR deterministic calculation route based on a simplified Phenix configuration

V Viallon, EYG Cervantes, L Buiron - Annals of Nuclear Energy, 2024 - Elsevier
Abstract Design and development of future reactor technologies rely on an intensive use of
computational tools for which confidence levels have to be quantified for each targeted …

Development and verification of lead-bismuth cooled fast reactor calculation code system Mosasaur

B Zhang, L Wang, L Lou, C Zhao, X Peng… - Frontiers in Energy …, 2023 - frontiersin.org
Lead-bismuth cooled fast reactor calculation code system named MOSASAUR has been
developed to meet the simulation requirements from LBFR engineering design. An overview …

Improvement of sodium fast reactor control rods calculations with APOLLO3

H Guo, G Martin, L Buiron - … on Advances in Nuclear Power Plants …, 2018 - cea.hal.science
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 …

A New Breakdown Methodology to Estimate Neutronic Model Biases Applied to APOLLO3 SFR Core Calculations

V Jouault, JM Palau, G Rimpault… - M&C 2017-International …, 2017 - cea.hal.science
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 …

Experimental validation of the new code package APOLLO3-SFR against ZPPR-10A experiment for critical and voided configurations

B Roque, A Rizzo, V Pascal, P Archier - PHYSOR 2016-International …, 2016 - cea.hal.science
In order to accurately compute the ASTRID4 $^{th} $ generation Sodium Fast Reactor (SFR)
prototype neutronic parameters, a new APOLLO3® deterministic code is under development …