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CCC-0754 VIM 5.1.

VIM 5.1, Steady-State 3-D Neutron Transport Using ENDF/B or Multigroup Cross Sections

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1. NAME OR DESIGNATION OF PROGRAM

VIM 5.1

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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
VIM 5.1 CCC-0754/01 Arrived 02-NOV-2009

Machines used:

Package ID Orig. computer Test computer
CCC-0754/01 Linux-based PC,SUN W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION

VIM is a continuous-energy criticality, reactor physics, and shielding code. It solves the transport problem for neutrons or photons, includes thermal neutron scattering effects, either in the eigenvalue mode or for photon or neutron fixed source. VIM features flexible geometry and neutron physics data carefully constructed from ENDF/B data. Special neutron physics capabilities in VIM include unresolved resonance probability tables, and direct treatment of resolved resonances described with Reich-Moore parameters. It has been extensively benchmarked, using both experiments and other accurate codes.

 

VIM solves the steady-state neutron or photon transport problem in any detailed three-dimensional geometry using either continuous energy-dependent ENDF nuclear data or multigroup cross sections. Neutron transport is carried out in a criticality mode, or in a fixed source mode (optionally incorporating subcritical multiplication). Photon transport is simulated in the fixed source mode. The geometry options are infinite medium, combinatorial geometry, and hexagonal or rectangular lattices of combinatorial geometry unit cells, and rectangular lattices of cells of assembled plates. Boundary conditions include vacuum, specular and white reflection, and periodic boundaries for reactor cell calculations.

 

The VIM 5.1 (April 2009) release includes data from ENDF/B-IV, ENDF/B-V, ENDF/B-VI and ENDF/B-VII.0. ASCII data libraries and a convenient means to convert them to binary on a target machine are included.

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4. METHODS

VIM uses standard Monte Carlo methods for particle tracking with several optional variance-reduction techniques. These include splitting/Russian roulette, non-terminating absorption with nonanalog weight cutoff energy. The keff is determined by the optimum linear combinations of two of the three eigenvalue estimates - analog, collision, and track length. Resonance and smooth cross sections are specified pointwise with linear - linear interpolation, frequently with many thousands of energy points. Unresolved resonances are described by the probability table method, which allows the statistical nature of the evaluated resonance cross sections to be incorporated naturally into the representation of self-shielding effects. Neutron interactions are elastic, inelastic and thermal scattering, (n,2n), fission, and capture, which includes (n,gamma), (n,p), (n,alpha), etc. Photon interaction data for pair production, coherent and incoherent scattering, and photoelectric events are taken from MCPLIB. Trajectories and scattering are continuous in direction, and anisotropic elastic and discrete level inelastic neutron scattering are described with probability tables derived from evaluated nuclear data. VIM has an automatic restart capability to permit user-directed statistical convergence. In eigenvalue calculations, the beginning source sites are from a random (flat) guess, or can be provided via ASCII input, or from a previous calculation. The starting neutrons for each subsequent generation are randomly selected from the potential fission sites in the previous generation.

 

Track-length or collision estimates of reaction rates are automatically tallied by energy group and edit region to facilitate comparison to other calculations. Groupwise edits include isotopic and macroscopic reaction rates and cross sections, group-to-group scattering cross sections, net currents, and scalar fluxes. Particle pseudo-collisions are used to estimate microscopic group-to-group (n,2n), inelastic, and PN elastic scattering. The serial correlation of eigenvalue estimates is computed to detect underestimated errors.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The maximum number of isotopes in one calculation is 100. The maximum of splitting surfaces is 60. All other problem characteristics are accommodated by variable dimensioning.

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6. TYPICAL RUNNING TIME

Varies widely, depending on geometric complexity, the number of isotopes, application of absorption weighting and splitting, overall scattering ratio, and desired statistics.

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8. RELATED OR AUXILIARY PROGRAMS
  • XSEDIT2 edits or performs binary conversion of processed physics data.

  • RETALLY repeats the statistical analysis of tally data, optionally collapsing energy groups and/or spatial regions, or skipping early generations.

  • KEFCODE repeats the statistical analysis of keff tallies.

  • ISOVIM produces multigroup VIM material files from COMPXS or ISOTXS interface files, or from CASMO ASCII output.

  • REBATCH regroups tally records to encompass more generations to permit assessment of serial correlation of reaction rate and flux estimates.

  • Slicer, a C++ program, generates color 2D shapshots of a specified VIM geometry.

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9. STATUS
Package ID Status date Status
CCC-0754/01 02-NOV-2009 Masterfiled Arrived
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10. REFERENCES
CCC-0754/01, included references:
- R. N. Blomquist:
VIM Monte Carlo Neutron/Photon Transport Code User's Guide Version 5.1,"
Web-based PDF file (March 2009)
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11. HARDWARE REQUIREMENTS
  • VIM was developed on Sun workstations and has been run on PCs (Linux) and Mac Pro.

  • Approximately 332MB is required to expand the distribution file.

  • An additional 1.3GB is required to expand the ASCII cross sections.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0754/01 C++, FORTRAN-90
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13. SOFTWARE REQUIREMENTS

VIM5.1 is written in Fortran 90 with a few routines in C. No executables are included in the package. This system was developed on Sun Solaris workstations and was ported to Linux and Mac Pro at ANL. The Mac Pro testing was done with Intel Compiler Version 11 under Darwin 9. VIM was tested at RSICC on an AMD Opteron in 32-bit mode under RedHat Enterprise Linux 4 using the Intel Compiler 10.1.0.018. Modification may be required on other systems. Over 1 GB of disk space is required to expand all of the included cross sections.

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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:   Argonne National Laboratory, Argonne, Illinois, USA

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16. MATERIAL AVAILABLE
CCC-0754/01
installation instructions
users guide
Fortran source
data libraries
test cases
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17. CATEGORIES
  • C. Static Design Studies
  • J. Gamma Heating and Shield Design

Keywords: ENDF/B, Monte Carlo method, combinatorial geometry, criticality, gamma ray, gamma ray heating, hexagonal lattices, multigroup theory, neutron, neutron transport equation, photon transport, reactor physics, rectangular, steady-state conditions, three-dimensional.