PSR-0365: MOCUP, MCNP/ORIGEN Coupling Utility Programs

OECD Nuclear Energy Agency / L'Agence pour l'énergie nucléaire

OECD-OCDE

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PSR-0365 MOCUP. (Abstract last modified 15-JUL-2003)

MOCUP, MCNP/ORIGEN Coupling Utility Programs

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION OF PROGRAM - MOCUP.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status MOCUP PSR-0365/01 Obsolete MOCUP PSR-0365/02 Tested

Machines used: Package-ID Orig.Computer Test Computer PSR-0365/02 Linux-based PC,DEC ALPHA W.S.,HP W.S. Linux-based PC,DEC ALPHA W.S.

3. DESCRIPTION OF PROGRAM OR FUNCTION - MOCUP is a series of utility and data manipulation programs to solve time and space-dependent coupled neutronics/isotopics problems.

4. METHODS - The neutronics calculation is performed by the Los Alamos National Laboratory code system, version 4a or later (CCC-200 or CCC-660),and the depletion and isotopics calculation is performed by CCC-371/ORIGEN2.1 developed at Oak Ridge National Laboratory. MCNP and ORIGEN2.1 are NOT included in this package. MOCUP consists of three utility programs (mcnpPRO, origenPRO, compPRO) to, respectively, search the MCNP output and tally files for relevant cell and tally parameters, prepare ORIGEN2.1 input files and execute the ORIGEN2.1 runs, and search ORIGEN2.1 punch files for relevant isotope concentrations and produce new MCNP input files. A graphical user interface is provided for execution convenience.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - At present, no mechanism exists for automatic serial execution of the program modules. The user must interface with the GUI to run each of the modules.

6. TYPICAL RUNNING TIME - For the sample problem provided, a two timestep calculation takes approximately 60 minutes on a DEC 5000. This includes the MCNP and ORIGEN2.1 calculations.

7. UNUSUAL FEATURES -

8. RELATED OR AUXILIARY PROGRAMS -

9. STATUS
PSR-0365/01: 15-JUL-2003 Obsolete
PSR-0365/02: 15-JUL-2003 Tested at NEADB

10. REFERENCES -
- J. F. Briesmeister, Ed.,
"MCNP - A General Monte Carlo N-Particle Transport Code, Version 4A," LA-12625-M (CCC-200)(November 1993).
- A. G. Croff,
"A Users' Manual for the ORIGEN2 Computer Code," ORNL/TM-7175 (CCC-371)(July 1980).
- R. S. Babcock, D. E. Wessol, C. A. Wemple, and S. C. Mason,
"The MOCUP Interface: A Coupled Monte Carlo/Depletion System," 1994 Topical Meeting on Advances in Reactor Physics, Knoxville, TN, p. III-368 (April 11-14, 1994).
PSR-0365/02:
- Legal disclaimer notice
- Letter to Steven Borror from Robert Fischer,
"Notification of Intent to Perfect Copyright in Computer Software
Entitled MOCUP" (June 23, 1995)
- R.L Moore, B.G. Schnitzler, C.A. Wemple, R.S. Babcock, D.E.Wessol,
"MOCUP: MCNP-ORIGEN2 Coupled Utility Program",
INEL-95/0523 (September 1995)

11. HARDWARE REQUIREMENTS - DEC Alpha workstations with OSF/1, DEC 5000 workstations with Ultrix, or HP workstations with HP/UX. The disk and memory requirements are dictated by MCNP and ORIGEN2.1.
Implementation has been limited to DEC Alpha workstations with OSF/1, DEC 5000 workstations with Ultrix, HP workstations with HP/UX, and PCs with Linux. Other implementations are not supported at this time.

12. PROGRAMMING LANGUAGE -PSR-0365/02: C-LANGUAGE

13. SOFTWARE REQUIREMENTS - Compilation requires an ANSI C compiler. X11R4, the Motif tool kit, MCNP and ORIGEN2.1 must be installed on the computer.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

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:
                Idaho National Engineering Laboratory
                Idaho Falls, Idaho, U.S.A.
Adaptation to Linux system by:
                Dr. Marcus SEIDL
                TUEV Sueddeutschland Bau and Betrieb GmbH
                BB-ETS3
                Westendstrasse 199
                D-80686 Muenchen
                Germany
                e-mail: marcus.seidl@tuev-sued.de

16. MATERIAL AVAILABLE -PSR-0365/02:
mocup.inf    Information file
mocup.pdf   Documentation and manual
Readme    Explanation of how to compile and run MOCUP.
cross.lib    structural material & activation product xsec library
fmt           Flux multiplier table for the sample problem.
Info     Notes for implementing CCC-371/ORIGEN2.1 on DEC Alpha and HP-UX.
inp.01   Initial (t=0) MCNP input for sample problem.
inp.02   MCNP input at the beginning of timestep 2 for the sample problem.
mason1   additional MCNP cross section data used in MOCUP test case.
mctal.01   MCNP tally file for timestep 1 for the sample problem.
Mocup   X toolkit variable settings to make the GUI look "pretty".
mpo.01.a   MOCUP data file for first timestep of sample problem.
mpo.01.b   MOCUP data file for second timestep of sample problem.
Nct    Nuclide correspondence table.
origen.ex   Execution script for ORIGEN2.
outp.01
run    Command line to run ORIGEN2.
skeleton.a   ORIGEN skeletal input file for first timestep of sample problem.
skeleton.b   ORIGEN skeletal input file second timestep of sample problem.
xsdir.mason   xsdir file for data in mason1.
\moi_files Directory of MOCUP-generated ORIGEN files for the sample problem
\srcdec  Directory containing MOCUP code source and makefile for DEC W.S.
\srchp  Dir. of source codes and makefile for HP workstations and LINUX machines

17. CATEGORIES  -

- L.  Data Preparation
- M.  Data Management

Keywords: BURNUP, NEUTRON,

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