RSICC CODE PACKAGE CCC‑ 647

 

 

1.         NAME AND TITLE

DRAGON 3.05D:           Lattice Cell Code System.

 

2.         CONTRIBUTOR

Ecole Polytechnique de Montreal, Quebec, Canada.

 

3.         CODING LANGUAGE AND COMPUTER

Fortran 77 and C; Intel Linux, IBM RS/6000, Sun  and MacOS (C00647MNYWS03).

 

4.         NATURE OF PROBLEM SOLVED

The computer code DRAGON contains a collection of models that can simulate the neutron behavior 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 supplied by means of standard libraries; resonance selfshielding calculations in multidimensional geometries; multigroup and multidimensional neutron flux calculations that 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.

DRAGON can access directly standard microscopic cross‑section libraries in the following formats: DRAGLIB, MATXS, WIMS-D4, WIMS‑AECL, and APOLLO.  It has the capability of exchanging macroscopic and microscopic cross‑section libraries with a code such as PSR‑206/ TRANSX‑CTR or PSR‑317/TRANSX‑2 by the use of the GOXS and ISOTXS format files.  Macroscopic cross sections can also be read in DRAGON via the input data stream.

See the developers’ website for additional information: http://www.polymtl.ca/nucleaire/DRAGON/en/index.php.

 

5.         METHOD OF SOLUTION

DRAGON contains a multigroup flux solver that can use various algorithms to solve the neutron transport equation for the spatial and angular distribution of the flux. Each of these algorithms is presented in the form of a one-group solution procedure where the contributions from other energy groups are considered as sources. The current release of DRAGON contains five such algorithms. The JPM option that solves the integral transport equation using the J+- method, (interface current method applied to homogeneous blocks); the SYBIL option that solves the integral transport equation using the collision probability method for simple one dimensional (1-D) or two dimensional (2-D) geometries and the interface current method for 2-D Cartesian or hexagonal assemblies; the EXCELL/NXT option to solve the integral transport equation using the collision probability method for more general 2-D geometries and for three dimensional (3-D) assemblies; the MOCC option to solve the transport equation using the method of cyclic characteristics in 2-D Cartesian, and finally the MCU option to solve the transport equation using the method of characteristics (non cyclic) for 3-D Cartesian geometries.

            The execution of DRAGON is managed via the GAN generalized driver. The code is modular and can be interfaced easily with other production codes the finite reactor code DONJON.

 

6.         RESTRICTIONS OR LIMITATIONS

None noted.

 

7.         TYPICAL RUNNING TIME

Not noted.

 

8.         COMPUTER HARDWARE REQUIREMENTS

DRAGON runs on IBM RS/6000, HP, and Sun workstations, MacOS and Linux on PC.

 

9.         COMPUTER SOFTWARE REQUIREMENTS

DRAGON runs under Unix, Linux, and MacOS operating systems; it can be run on Windows-based PC under Cygwin.  At RSICC the system was successfully tested on an IBM RS/6000 under AIX 5.1 with XL Fortran version 8.01 and on an Intel PC under RedHat 9 Linux with the GNU g77 (gcc version 3.2.2) compiler.

 

10.        REFERENCES

a)         included in documentation:

G. Marleau, A. Hebert, and R. Roy, “A User Guide for DRAGON, 3.05D,” IGE‑174 Rev. 6D (March 2007).

 

b)         included only in electronic pdf files on CD (will extract to the Guides subdirectory):

R. ROY and A. HEBERT, “The GAN Generalized Driver” (March 2000) (IGE158.pdf)

R. ROY, “The CLE-2000 tool-box” (December 1999) (IGE163.pdf)

A. HEBERT, G. MARLEAU and R. ROY, “A Description of the Data Structures for DRAGON 3.05D,” Technical report IGE-232 Rev. 4D, (March 2007) (IGE232R4D.pdf).

G. MARLEAU, “The Excell Geometries Numbering Scheme in Dragon,” Technical report IGE-233 (December 1997) (IGE233.pdf).

G. MARLEAU, “DRAGON Theory Manual - Part 1: Collision Probability Calculations,” Technical report IGE-236 Revision 1 (October 2001) (IGE236R1.pdf).

G. MARLEAU and E. VARIN, “An History Interface Between Dragon And Donjon, The Hst: Module,” Technical report  IGE-259 R1 (December 2004) (IGE259R1.pdf)

 

11.        CONTENTS OF CODE PACKAGE

Included are the referenced documents and a CD‑ROM in a GNU compressed Unix tar file which contains installation instructions, documentation, Fortran source, installation scripts, and test input and output for AIX, Linux and Mac.

 

12.        DATE OF ABSTRACT

December 1997, revised March 1998, December 2002, November 2007.

 

KEYWORDS:   BURNUP; CELL CALCULATION; COMPLEX GEOMETRY; NEUTRON; REACTOR PHYSICS; WORKSTATION