[PDF][PDF] The JEFF-3.1. 1 nuclear data library

A Santamarina, D Bernard, P Blaise, M Coste… - JEFF report, 2009 - Citeseer
The NEA Data Bank provides nuclear data and computer program services for participating
countries. In these and related tasks, the NEA works in close collaboration with the …

[引用][C] Applied Reactor Physics

A Hebert - Presses Inter Polytechnique, 2009 - books.google.com
Page 1 L - (8+N) N 48 2 q=4 points q=N-2p+(5/2) q=6=N-2p+2 Applied Reactor Physics
Cos Wa D UT TONER PRESSES INTERNATIONALES POLYTECHNIQUE Alain Hébert …

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 …

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 …

A neutron transport characteristics method for 3D axially extruded geometries coupled with a fine group self-shielding environment

S Santandrea, D Sciannandrone… - Nuclear Science and …, 2017 - Taylor & Francis
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 …

[PDF][PDF] APOLLO2. 8: a validated code package for PWR neutronics calculations

A Santamarina, D Bernard, P Blaise, L Erradi… - Proc. Int. Conf …, 2009 - researchgate.net
This paper summarizes the Qualification work performed to demonstrate the accuracy of the
new APOLLO2. 8/SHEM-MOC package based on JEFF3. 1.1 nuclear data file for the …

Optimized tracking strategies for step MOC calculations in extruded 3D axial geometries

D Sciannandrone, S Santandrea, R Sanchez - Annals of Nuclear Energy, 2016 - Elsevier
Specialized tracking techniques have been developed for a step-characteristics transport
solver. These techniques strongly exploit the regularities of extruded 3D axial geometries to …

New numerical solution with the method of short characteristics for 2-d heterogeneous cartesian cells in the apollo2 code: Numerical analysis and tests

E Masiello, R Sanchez, I Zmijarevic - Nuclear Science and …, 2009 - Taylor & Francis
The method of short characteristics is extended to two-dimensional heterogeneous
Cartesian cells. The new application is intended for realistic pin-by-pin lattice calculations …

Unstructured partial-and net-current based coarse mesh finite difference acceleration applied to the extended step characteristics method in NEWT

KS Kim, MD DeHart - Annals of Nuclear Energy, 2011 - Elsevier
The NEWT (NEW Transport algorithm) code is a multi-group discrete ordinates neutral-
particle transport code with flexible meshing capabilities. This code employs the Extended …

A linear surface characteristics approximation for neutron transport in unstructured meshes

S Santandrea, R Sanchez, P Mosca - Nuclear science and …, 2008 - Taylor & Francis
The method of characteristics (MOC) in unstructured meshes has become a standard for
reactor physics applications. One of the major drawbacks of the MOC is the difficulty to …