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CCC-0647 DRAGON.

DRAGON, Reactor Cell Calculation System with Burnup

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1. NAME OR DESIGNATION OF PROGRAM:  DRAGON3.02
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters 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.
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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.
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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.
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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.
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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.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
CCC-0647/02 08-AUG-2002 Masterfiled Arrived
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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)
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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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0647/02 FORTRAN-77
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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.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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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
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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)
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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.