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CCC-0777 COG 11.

COG 11, Multiparticle Monte Carlo Code System for Shielding and Criticality Use

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1. NAME OR DESIGNATION OF PROGRAM

COG 11

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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
COG 11 CCC-0777/01 Arrived 13-APR-2011

Machines used:

Package ID Orig. computer Test computer
CCC-0777/01 Linux-based PC,PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

COG is a modern, full-featured Monte Carlo radiation transport code that provides accurate answers to complex shielding, criticality, and activation problems.COG was written to be state-of-the-art and free of physics approximations and compromises found in earlier codes. COG is fully 3-D, uses point-wise cross sections and exact angular scattering, and allows a full range of biasing options to speed up solutions for deep penetration problems. Additionally, a criticality option is available for computing Keff for assemblies of fissile materials. ENDL or ENDFB cross section libraries may be used. COG home page: http://cog.llnl.gov

 

Cross section libraries are included in the package. COG can use either the LLNL ENDL-90 cross section set or the ENDFB/VI set. Analytic surfaces are used to describe geometric boundaries. Parts (volumes) are described by a method of Constructive Solid  Geometry. Surface types include surfaces of up to fourth order, and pseudo-surfaces such as boxes, finite cylinders, and figures of revolution. Repeated assemblies need be defined only once. Parts are visualized in cross-section and perspective picture views. A lattice feature simplifies the specification of regular arrays of parts. Parallel processing under  MPI is supported for multi-CPU systems.

 

Source and random-walk biasing techniques may be selected to improve solution statistics. These include source angular biasing, importance weighting, particle splitting and Russian roulette, pathlength stretching, point detectors, scattered direction biasing, and forced collisions.

 

Criticality - For a fissioning system, COG will compute Keff by transporting batches of neutrons through the system.

 

Activation - COG can compute gamma-ray doses due to neutron-activated materials, starting with just a neutron source.

 

Coupled Problems - COG can solve coupled problems involving neutrons, photons, and electrons.

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4. METHODS

COG uses Monte Carlo methods to solve the Boltzmann transport equation for particles traveling through arbitrary 3-dimensional geometries. Neutrons, photons, electrons, and protons can be transported. Electron transport uses the EGS transport kernel.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Size of problems may be limited by computer memory. COG will transport neutrons with energies in the range of 10-5 eV to 150 MeV, protons with energies up to hundreds of GeV, and photons with energies in the range of 10 eV to 100 GeV. (COG?s energy ranges are limited by the available cross section sets and physics models). Via the EGS4 electron transport kernel, electrons in the range of 10 keV to a few thousand GeV can also be transported.

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6. TYPICAL RUNNING TIME

Running time on a particular computer will vary widely, depending on geometric complexity, number of materials, and number of particles to be followed. For many problems, runs of a few minutes may give an approximate solution. For a statistically precise solution, hours of computation may be necessary. The parallel processing option is useful for shortening the run times of long problems.

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8. RELATED DATA LIBRARIES

The following data libraries are included in this distribution:
Neutron:

  • ENDFB7R0- Data pre-processed from the Brookhaven ENDF/B-VII Release 0 nuclear database.

  • ENDFB6R8- Data pre-processed from the Brookhaven ENDF/B-VI Release 8 nuclear database.

  • ENDFB6R7- Data pre-processed from the Brookhaven ENDF/B-VI Release 7 nuclear database.

  • ENDL90- The LLNL ENDL-90 nuclear database.

  • RED2002- A hybrid ENDFB/ENDL database developed by Red Cullen at LLNL.

  • COGSAB- Thermal scattering database using S(a,b) model.

 

Photon:

  • COGGXS- The LLNL EPDL photon database.

 

Charged Particles:

  • elossr- Proton stopping powers

  • Landau- Proton straggling data

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9. STATUS
Package ID Status date Status
CCC-0777/01 13-APR-2011 Masterfiled Arrived
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10. REFERENCES
  • R.J. Howerton, R.E. Dye, and S.T. Perkins: "Evaluated Nuclear Data", Library Lawrence Livermore National Laboratory, Livermore, CA, UCRL-50400, Vol. 4, Rev. 1 (1981).

  • R. Kinsey: "Data Formats and Procedures for the Evaluated Nuclear Data File ENDF," National Nuclear Data Center, Brookhaven National Laboratory, Upton NY BNL-NCS-50496 (1979).

  • W. R. Nelson, H. Hirayama, and D. W. O. Rogers: "The EGS4 Code System", SLAC-Report #265, Stanford University (December, 1985).

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11. HARDWARE REQUIREMENTS

Supported platforms include Intel/Linux and Intel/Windows. Expanding the code system and running test cases requires 170 MB of hard disk space.

 

Supported platforms are: PC workstations running Windows 7 OS or Windows XP; Workstations/Clusters running Linux OS. The code system without the data libraries requires 35 MB of disk space. The standard data library set requires 1.6 GB.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0777/01 C-LANGUAGE, FORTRAN
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13. SOFTWARE REQUIREMENTS

Fortran and C source files are not included in this package. Bash SHELL is required to run the installation scripts. The code uses graphics routines from the PGPLOT subroutine library.  The package includes executables created on: Dell 560 with Intel Q8300 processor running Windows 7 OS, GNU gfortran and gcc compilers; Intel Xeon processors running GNU/Linux OS, GNU gfortran and gcc compilers.

 

At RSICC, test cases were run using included executables on: Intel under Windows XP SP3  and Windows 7 and  Red Hat Linux.

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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:   Lawrence Livermore National Laboratory
                Livermore, California, USA

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16. MATERIAL AVAILABLE
CCC-0777/01
executables for Windows and Linux
data libraries
test cases
documentation
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17. CATEGORIES
  • C. Static Design Studies
  • J. Gamma Heating and Shield Design

Keywords: Monte Carlo method, activation, complex geometry, coupled, criticality, cross sections, electrons, gamma-ray, neutron, protons.