From 7dfcc480ba1e19bd3232349fc733caef94034292 Mon Sep 17 00:00:00 2001 From: stainer_t Date: Mon, 8 Sep 2025 13:48:49 +0200 Subject: Initial commit from Polytechnique Montreal --- doc/IGE335/Summary.tex | 40 ++++++++++++++++++++++++++++++++++++++++ 1 file changed, 40 insertions(+) create mode 100644 doc/IGE335/Summary.tex (limited to 'doc/IGE335/Summary.tex') diff --git a/doc/IGE335/Summary.tex b/doc/IGE335/Summary.tex new file mode 100644 index 0000000..df08fd7 --- /dev/null +++ b/doc/IGE335/Summary.tex @@ -0,0 +1,40 @@ +\clearpage +$ $ +\vskip 2.0cm + +\begin{center} + +SUMMARY + +\end{center} + +The computer code DRAGON contains a collection of models which can simulate the +neutronic behaviour of a unit cell or a fuel assembly in a nuclear reactor. It +includes all of the functions that characterize a lattice cell code, namely: the +interpolation of microscopic cross sections which are supplied by means of +standard libraries; resonance self-shielding calculations in multidimensional +geometries; multigroup and multidimensional neutron flux calculations which can +take into account neutron leakage; transport-transport or transport-diffusion +equivalence calculations as well as editing of condensed and homogenized nuclear +properties for reactor calculations; and finally isotopic depletion calculations. + +\vskip 0.15cm + +The code DRAGON contains a multigroup iterator conceived to control a number of +different algorithms for the solution of the neutron transport equation. Each of +these algorithms is presented in the form of a one-group solution procedure +where the contributions from other energy groups are included in a source term. +The current version of DRAGON contains many such algorithms. The +SYBIL option which solves the integral transport equation using the collision +probability method for simple one-dimensional (1--D) geometries (either plane, +cylindrical or spherical) and the interface current method for 2--D Cartesian or hexagonal +assemblies. The EXCELL, NXT and SALT options which solves the integral transport equation +using the collision probability method for general 2--D geometries and for +three-dimensional (3--D) assemblies. The MCCG option solves the integro-differential +transport equation using the long characteristics method for general 2--D and +3--D geometries. + +\vskip 0.15cm + +The execution of DRAGON is controlled by the CLE-2000 supervisor. It is +modular and can be interfaced easily with other production codes. -- cgit v1.2.3