MCNP-DSP: Monte Carlo N‑Particle Transport Code System with Digital Signal Processing.
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.
MCNP-DSP includes a test library of cross sections for running the sample problems, but the test library is not suitable for real problems. Running the code requires continuous energy cross section data included in DLC‑189/MCNPXS or equivalent data.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Fortran 77 and C; SUN and DEC UNIX workstations
Fortran 77; MS‑DOS PCs (C00699MNYCP00).
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‑α) measurements, pulsed neutron measurements, Feynman variance measurements, and multiplicity measurements. CCC‑700/MCNP4C is recommended for general purpose calculations.
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.
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.
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.
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
The Adobe Acrobat Reader freeware is available from http://www.adobe.com to read and print the electronic documentation.
a. included documentation in hardcopy and electronic format on CD in DOC/C699DOC.PDF:
Tim Valentine, AReadme.txt (October 2000).
T. E. Valentine, MCNP‑DSP Users Manual, ORNL/TM‑13334 R2 (January 2001).
Appendix G from CCC-660/MCNP4B2 which corresponds to DLC-189/MCNPXS libraries.
b. included only in electronic format on CD in DOC/C200DOC.PDF:
J. F. Briesmeister, Ed., MCNP - A General Monte Carlo N-Particle Transport Code, Version 4A, LA-12625-M (1993).
Included are the referenced documents in (10a and 10b) and the source codes, test problems, PC executables, and installation scripts transmitted on CD in both DOS and UNIX formats. As a convenience to users, the DLC-189/MCNPXS data library (in ASCII mode) is included on the distribution media. See the Readme.txt file for details on package contents and installation.
KEYWORDS: COMPLEX GEOMETRY; COUPLED; CROSS SECTIONS; ELECTRON; GAMMA-RAY; MICROCOMPUTER; MONTE CARLO; NEUTRON; WORKSTATION