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CCC-0699 MCNP-DSP.

MCNP-DSP, Monte Carlo Neutron-Particle Transport Code with Digital Signal Processing

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1. NAME OR DESIGNATION OF PROGRAM:  MCNP-DSP.
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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.

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Machines used:

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3. DESCRIPTION OF PROGRAM OR FUNCTION

MCNP-DSP is recommended only for experienced MCNP users working with subcritical measurements. It is a modification of the Los Alamos National Laboratory's Monte Carlo code MCNP4a that is used to simulate a variety of subcritical measurements. The DSP version was developed to simulate frequency
analysis measurements, correlation (Rossi-) measurements, pulsed neutron measurements, Feynman variance measurements, and multiplicity measurements. CCC-700/MCNP4C is recommended for general purpose calculations.
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4. METHODS

MCNP-DSP performs calculations very similarly to MCNP and uses the same generalized geometry capabilities of MCNP. MCNP-DSP can only be used with the continuous-energy cross-section data. A variety of source and detector options are available. However, unlike standard MCNP, the source and detector options are limited to those described in the manual because these options are specified in the MCNP-DSP extra data file. MCNP-DSP is used to obtain the  time-dependent response of detectors that are modeled in the simulation geometry. The detectors represent actual detectors used in measurements. These time-dependent detector responses are used to compute a variety of quantities such as frequency analysis signatures, correlation signatures, multiplicity signatures, etc., between detectors or sources and detectors. Energy ranges are 0-60 MeV for neutrons (data generally only available up to 20 MeV) and 1 keV - 1 GeV for photons and electrons.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME

Runtimes vary greatly. The included test cases ran in 3.5 hours on a DEC 500 AU, 22.5 hours on a Sun SparcStation 20, and ~5 hours on a Pentium III 550 MHz PC.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

AUXILIARY PROGRAMS:

PRPR: Pre-processor for Extracting the Various Hardware Versions of
      MCNP.
MAKXSF: Preparer of MCNP Cross-Section Libraries.

RELATED DATA LIBRARY:

DLC-189/MCNPXS: Standard cross sections based on ENDF/B-V and ENDF/B-VI.
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9. STATUS

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10. REFERENCES
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11. HARDWARE REQUIREMENTS

MCNP-DSP is operable on SUN and DEC Unix workstations and on personal computers that have at least 8 MB memory with an 80486 processor.
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12. PROGRAMMING LANGUAGE(S) USED

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13. SOFTWARE REQUIREMENTS

A Fortran 77 compiler is needed to install MCNP-DSP. Any Fortran 77 compiler on the SUN or DEC Unix operating system should suffice. A C compiler with an ANSI C library is required for the Unix operating system. Compilation of the PC version requires Lahey Fortran F77L-EM/32 V5.2; an executable created with this compiler is included for PC users. The code was tested at RSICC on the following systems.

1. DEC 500 AU under Digital Unix 4.0D with DEC Fortran 5.1-8 and
   DEC C 5.6-075
2. Sun SparcStation 20 SunOS 5.7 Fortran 77 5.0 patch 107596-02
3. Sun UltraSparc Solaris 2.6 Fortran 77 5.0 and C Version 5.0
4. Pentium III 550MHz in a DOS window of Windows NT with Lahey
   F77L-EM/32 V5.2
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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, U. S. A.

Developed by:   Oak Ridge National Laboratory, Oak Ridge,
                Tennessee, U.S.A.
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16. MATERIAL AVAILABLE
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17. CATEGORIES
  • C. Static Design Studies
  • J. Gamma Heating and Shield Design

Keywords: Monte Carlo method, coupled neutron gamma cross sections, processing, shielding.