APOLLO2 year 2010
R Sanchez, I Zmijarevi, M Coste-Delclaux… - Nuclear engineering …, 2010 - koreascience.kr
This paper presents the mostortant developments implemented in the APOLLO2 spectral
code since its last general presentation at the 1999 M&C conference in Madrid. APOLLO2 …
code since its last general presentation at the 1999 M&C conference in Madrid. APOLLO2 …
A linear source approximation scheme for the method of characteristics
RM Ferrer, JD Rhodes III - Nuclear Science and Engineering, 2016 - Taylor & Francis
A linear source (LS) approximation scheme is presented for the two-dimensional method of
characteristics (MOC). The LS approximation relies on the computation of track-based …
characteristics (MOC). The LS approximation relies on the computation of track-based …
GENESIS: a three-dimensional heterogeneous transport solver based on the Legendre polynomial expansion of angular flux method
A Yamamoto, A Giho, Y Kato, T Endo - Nuclear Science and …, 2017 - Taylor & Francis
A heterogeneous transport solver in three-dimensional (3-D) geometry, GENESIS, is
developed incorporating recent developments in the method of characteristics (MOC) in 3-D …
developed incorporating recent developments in the method of characteristics (MOC) in 3-D …
Prospects in deterministic three-dimensional whole-core transport calculations
R Sanchez - Nuclear Engineering and Technology, 2012 - koreascience.kr
The point we made in this paper is that, although detailed and precise three-dimensional
(3D) whole-core transport calculations may be obtained in the future with massively parallel …
(3D) whole-core transport calculations may be obtained in the future with massively parallel …
Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor
S Santandrea, L Graziano, D Sciannandrone - Annals of Nuclear Energy, 2018 - Elsevier
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 …
treatment of 3D extruded geometries has been developed inside the TDT code of APOLLO3 …
[PDF][PDF] Linear source approximation in CASMO5
ABSTRACT A Linear Source (LS) approximation has been implemented in the two-
dimensional Method of Characteristics (MOC) transport solver in a prototype version of …
dimensional Method of Characteristics (MOC) transport solver in a prototype version of …
The linear source approximation and particle conservation in the Method of Characteristics for isotropic and anisotropic sources
RM Ferrer, JD Rhodes III - Annals of Nuclear Energy, 2018 - Elsevier
Particle conservation, otherwise known as particle balance, is one of the main properties to
examine when considering any transport discretization. In the past, particle conservation has …
examine when considering any transport discretization. In the past, particle conservation has …
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations
S Choi, A Fitzgerald, N Herring… - Nuclear Science and …, 2024 - Taylor & Francis
This work seeks to improve upon an existing formulation of the Method of Characteristics
(MOC) with a Linear Source Approximation (LSA) for problems that use nonconstant cross …
(MOC) with a Linear Source Approximation (LSA) for problems that use nonconstant cross …
Analyse et développement d'outils numériques déterministes et stochastiques résolvant les équations du bruit neutronique et applications aux réacteurs thermiques et …
A Rouchon - 2016 - theses.hal.science
Le bruit neutronique désigne les fluctuations de la population neutronique induites par des
changements déterministes ou stochastiques des sections efficaces macroscopiques lors du …
changements déterministes ou stochastiques des sections efficaces macroscopiques lors du …
Solution of the neutron transport equation by the Method of Characteristics using a linear representation of the source within a mesh
T Mazumdar, SB Degweker - Annals of Nuclear Energy, 2017 - Elsevier
A common assumption in the solution of the neutron transport equation by the Method of
Characteristics (MOC) is that the source (or flux) is constant within a mesh. This assumption …
Characteristics (MOC) is that the source (or flux) is constant within a mesh. This assumption …