Computer Programs
CCC-0647 DRAGON.
last modified: 25-APR-2007 | catalog | categories | new | search |

CCC-0647 DRAGON.

DRAGON, Reactor Cell Calculation System with Burnup

top ]
1. NAME OR DESIGNATION OF PROGRAM:  DRAGON3.02
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
DRAGON3.02 CCC-0647/02 Arrived 08-AUG-2002

Machines used:

Package ID Orig. computer Test computer
CCC-0647/02 IBM RISC6000 WS,HP W.S.,SUN W.S.,DEC ALPHA W.S.
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

DRAGON is a collection of models to simulate the neutronic 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: interpolation of microscopic cross sections 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.
The user must supply cross sections. DRAGON can access directly standard microscopic cross-section libraries in the following formats: DRAGON, MATXS (TRANSX-CTR), WIMSD4, WIMS-AECL, and APOLLO. It has the capability of exchanging macroscopic and microscopic cross-section libraries with a code such as PSR-0206/TRANSX-CTR or PSR-0317/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.
top ]
4. METHOD OF SOLUTION

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.
CCC-0647/02
The current  version, DRAGON_971124 (Release 3.02), which was released in January 1998, contains three such algorithms. The JPM option solves the integral transport equation using the interface current method applied to homogeneous blocks; the SYBIL option 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; and the EXCELL option solves the integral transport equation using the collision probability method for more general 2-D geometries and for the three-dimensional (3-D) assemblies. The execution of DRAGON is controlled by the generalized GAN driver, which is modular and can be interfaced easily with other production codes.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

There are some limitations in the 2-D and 3-D geometries that can be treated. For example, 3-D fuel cluster cannot be analyzed in the current version  of the code.
top ]
6. TYPICAL RUNNING TIME

The test cases in the "macrolib" directory ran in 178 seconds of wall clock time on an IBM RS/6000 Model 590 under AIX 4.2.
top ]
7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
top ]
8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
top ]
9. STATUS
Package ID Status date Status
CCC-0647/02 08-AUG-2002 Masterfiled Arrived
top ]
10. REFERENCES
CCC-0647/02, included references:
- G. Marleau:
  README
  (December 1997)
- G. Marleau, A. Hebert, R. Roy:
  A User's Guide for DRAGON.
  IGE-174 Rev.3 (December 1997)
- G. Marleau, A. Herbert, R. Roy:
  A Description of the DRAGON Data Structures.
  IGE-232 (December 1997)
top ]
11. MACHINE REQUIREMENTS:  DRAGON runs on IBM RS/6000 and HP9000/700 workstations.
CCC-0647/02
DRAGON runs on IBM RS/6000 and HP9000/700 workstations, SUN SparcStations and DEC Alpha systems.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0647/02 FORTRAN-77
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

At RSICC the
system was successfully tested on an IBM RSIC/6000 model 590 under
AIX 4.2 with xlf90 version 3.2.2 and an HP Model 715 under HP-UX-10.20 using f77 compiler version 10.20.01.
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, USA

Developed by:   Ecole Polytechnique de Montreal
                MONTREAL, Quebec, Canada
top ]
16. MATERIAL AVAILABLE
CCC-0647/02
MISTP: README Instructions to install DRAGON
SRCTP: DECKLS_SRC Program to divide DRAGON and GANLIB sources into files
SRCTP UPD1P3_SRC Prepares machine dependent versions of DRAGON and GANLIB files
LBBTP: LIBSETUP Microscopic cross-section libraries installation script
SRCTP: UPD1P3_SRC Prepares machine dependent versions of DRAGON and GANLIB files
SRCTP: REMTIM_SRC Program to remove time stamps from DRAGON output file
DATTP: CLEAN Script to clean up after program installation
DATTP: MAKPROG Main Unix installation script
DATTP: RDRAGON DRAGON Unix execution script
SRCTP: DRAGON_971124 Source file for DRAGON
DATTP: UPDPROG Secondary Unix installation script
DATTP: macrolib Subdir. of test cases based on macroscopic cross-sections
DATTP: matxslib Subdir. of test cases for MATXS microscopic cross section libraries
DATTP: wimsd4 Subdir. of test cases for WIMSD4 microscopic cross section librar.
REPPT: README (December 1997)
REPPT: IGE-174 Rev. 3 (December 1997)
REPPT: IGE-232 (December 1997)
top ]
17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • C. Static Design Studies
  • K. Reactor Systems Analysis

Keywords: burnup, cell calculation, depletion, fuel management, neutron transport equation.