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USCD1234 DRAGON 3.05D.

DRAGON 3.05D, Reactor Cell Calculation System with Burnup

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1. NAME OR DESIGNATION OF PROGRAM:  DRAGON 3.05D
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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
DRAGON 3.05D USCD1234/01 Tested 18-MAY-2011

Machines used:

Package ID Orig. computer Test computer
USCD1234/01 Linux-based PC,UNIX W.S. Linux-based PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

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.
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4. METHODS

The code DRAGON contains a multigroup flux solver conceived that can use a 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.
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8. RELATED OR AUXILIARY PROGRAMS

DRAGON can access directly microscopic cross-section libraries defined according to the following standard formats: DRAGLIB, MATXS, WIMS-D4 and WIMS-AECL. It has the capability of exchanging macroscopic cross-section libraries with a code such as TRANSX-CTR or TRANSX-2 by the use of GOXS and ISOTXS format files. The macroscopic cross section can also be read in DRAGON via the input data stream.
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9. STATUS
Package ID Status date Status
USCD1234/01 18-MAY-2011 Tested at NEADB
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10. REFERENCES
USCD1234/01, included references:
- Robert ROY and Alain HEBERT:
The GAN Generalized Driver (March 2000) (IGE158.pdf)
- Robert ROY:
The CLE-2000 tool-box (December 1999) (IGE163.pdf)
- G. MARLEAU, A. HEBERT and R. ROY:
A User Guide for DRAGON 3.05D (Technical report IGE-174 Rev. 6D, March 2007)
- 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)
- G. MARLEAU:
The Excell Geometries Numbering Scheme in Dragon
(Technical report IGE-233, December 1997)
- G. MARLEAU:
DRAGON Theory Manual - Part 1: Collision Probability Calculations
(Technical report IGE-236 Revision 1, October 2001)
- G. MARLEAU and E. VARIN:
An History Interface Between Dragon And Donjon:
The Hst: Module
(Technical report  IGE-259 R1, December 2004)
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11. HARDWARE REQUIREMENTS
USCD1234/01
This package was tested at the NEA Databank on:
- COMPUTER : Apple iMac i7 2800MHz
- OPERATING SYSTEM : Ubuntu Linux 9.10 Kernel 2.6
- COMPILER : fort77 Version 1.15
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Institut d'Energetique
Ecole Polytechnique de Montreal
Case Postale 6079
succ. Centre-Ville
MONTREAL, QUEBEC H3C 3A7
Canada
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16. MATERIAL AVAILABLE
USCD1234/01
COPYRIG~.TXT: text file containing the DRAGON copyright
README.TXT: the file you are currently reading
Guides: directory containing the IGE reports associated with DRAGON, GANLIB and
CLE-2000
Sources: source code for DRAGON and GANLIB and scripts for the dragon
installation
Tests: test cases and dragon running scripts
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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.