The MOCUP code system is a series of pre- and post-processor modules to connect the MCNP Monte Carlo transport code and the ORIGEN2.1 depletion and isotopics code into a generalized transport/depletion package for use on non-lattice or non-uniform lattice reactor calculations. No modifications were made to either MCNP or ORIGEN2.1, permitting standard versions of each code to be used. MOCUP contains a simple graphical user interface to allow the user to easily execute the modules governing MCNP and ORIGEN2.1 input assembly, output processing, and execution, and to perform various file housekeeping tass. Flux and reaction rate calculations are performed in MCNP, with the results extracted by the menpPRO module and passed to the ORIGEN2.1 code by the origenPRO module for deletion. The resulting new isotopic inventories are used to modify the MCNP input in the compPRO module for use in the next timestep. MOCUP permits an arbitary number of depletable cells, different depletable cell types (fuel, targets, etc.) and isotopes that may be tracked. anticipated applications are to test and research reactor physics analyses; isotope production; fuel, target, filter, control, and/or burnable absorber depletion; structural material transmutation; and verification of lattice code calculations.
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Moore, R. L., Schnitzler, B. G., Wemple, C. A., and Babcock, R. S. MCNP-ORIGEN2 Coupling Utility Program.
Computer software. Vers. 00. DOE/ER. 30 Jul. 1997.
Web.
Moore, R. L., Schnitzler, B. G., Wemple, C. A., & Babcock, R. S. (1997, July 30). MCNP-ORIGEN2 Coupling Utility Program (Version 00) [Computer software].
Moore, R. L., Schnitzler, B. G., Wemple, C. A., and Babcock, R. S. MCNP-ORIGEN2 Coupling Utility Program.
Computer software. Version 00. July 30, 1997.
@misc{osti_1230391,
title = {MCNP-ORIGEN2 Coupling Utility Program, Version 00},
author = {Moore, R. L. and Schnitzler, B. G. and Wemple, C. A. and Babcock, R. S.},
abstractNote = {The MOCUP code system is a series of pre- and post-processor modules to connect the MCNP Monte Carlo transport code and the ORIGEN2.1 depletion and isotopics code into a generalized transport/depletion package for use on non-lattice or non-uniform lattice reactor calculations. No modifications were made to either MCNP or ORIGEN2.1, permitting standard versions of each code to be used. MOCUP contains a simple graphical user interface to allow the user to easily execute the modules governing MCNP and ORIGEN2.1 input assembly, output processing, and execution, and to perform various file housekeeping tass. Flux and reaction rate calculations are performed in MCNP, with the results extracted by the menpPRO module and passed to the ORIGEN2.1 code by the origenPRO module for deletion. The resulting new isotopic inventories are used to modify the MCNP input in the compPRO module for use in the next timestep. MOCUP permits an arbitary number of depletable cells, different depletable cell types (fuel, targets, etc.) and isotopes that may be tracked. anticipated applications are to test and research reactor physics analyses; isotope production; fuel, target, filter, control, and/or burnable absorber depletion; structural material transmutation; and verification of lattice code calculations.},
doi = {},
url = {https://www.osti.gov/biblio/1230391},
year = {Wed Jul 30 00:00:00 EDT 1997},
month = {Wed Jul 30 00:00:00 EDT 1997},
note =
}
Medium: X; OS: DEC Ultrix (version 4.3a or higher) and OSFI/1; HP/UX (Version 9.0 or higher); IBM AIX. Requires that the X11R4 window environment and Motif toolkit be installed.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
