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NEA-1643 MCB1C.

MCB1C, Monte-Carlo Continuous Energy Burnup Code

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1. NAME OR DESIGNATION OF PROGRAM:  MCB.
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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
MCB1C NEA-1643/01 Tested 30-AUG-2002

Machines used:

Package ID Orig. computer Test computer
NEA-1643/01 Linux-based PC,UNIX W.S. Linux-based PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

MCB is a Monte Carlo Continuous Energy Burnup Code for a general-purpose use to calculate a nuclide density time evolution with burnup or decay. It includes eigenvalue calculations of critical and subcritical systems as well as neutron transport calculations in fixed source mode or k-code mode to obtain reaction rates and energy deposition that are necessary for burnup calculations.
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4. METHODS

The code integrates the code MCNP4C, which is used for neutron transport calculation, and a novel Transmutation Trajectory Analysis code (TTA), which serves for density evolution calculation, including formation and analysis of the transmutation chain. MCB is compatible with MCNP and preserves the structure of it. Complete burnup calculations can be done in a one single run and it requires preparation of only one input file by a modest modification of an MCNP input file.  The code was extensively tested in benchmark calculations and reactor core designing. The general conclusion from practical application shows that MCB1C produces valuable results that are physically inherent and the correctness of physical model applied has been proved. MCB1C has been also equipped with new features among them the simulation of material processing including continuous feeding of materials is the most important. Development of the code was addressed towards improving calculation effectiveness and system diagnostic and towards improving physical model for rigid treatment but also providing simplified model option for quick design studies or benchmarks.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

About 2.5 hours are required for complete installation of the package (including compilation/link of the MCB-1C code and the ASCII to binary conversion of all the nuclear data libraries). The 4 test cases ran in approx. 10 minutes on a PC DELL PowerEdge 1550 Bi 1GHz.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

The MCB systems is build on MCNP4C foundation and requires the following executable files from MCNP processing systems:
- PRPR: Pre-processor for Extracting the Various Hardware Versions of MCNP and other codes.
- MAKXSF: Preparer of MCNP Cross-Section Libraries.
- FSPLIT: Splits the fortran source into subroutines
- mcnp4c.id: the main MCNP4C codef file (not patched by patchf files)
- mcnpc.id: the c subroutines for MCNP4C codef file

These files are not included in this distribution and are provided with the MCNP-4C package (should be requested separately).

RELATED DATA LIBRARY

The MCB system consists of following libraries, which are distributed with the code package for the convenience of users:
- The burnup library - BPLIB (included in NEA-1643/01 package)
- ENDFB6.8 cross section library (NEA-1669/01 and NEA-1669/02 packages)
- JEF2.2 cross section library (NEA-1667/01 package)
- JENDL3.2 cross section library (NEA-1670/01, NEA-1670/02 and NEA-1670/03 packages)
- Transport libraries DLC200 (DLC-200/04 package)
- Dosimetry cross sections library EAF99 (NEA-1668/01 package)

Hard disk space of 15 GB temporarily available during installation of all cross section libraries makes the installation smooth and easy. Decompressed ASCII files of cross section libraries occupy most of the HD space. The binary libraries after installations take HD space as follows: ENDFB6.8 - 905 MB, JEF2.2 - 547 MB, JENDL3.2 - 1.3 GB, DLC200 - 173 MB, EAF99 - 222 MB, and all together about 3.2 GB. For most of the applications the installation of one transport cross section library will be sufficient, but for particular needs the user can install even all of them.
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9. STATUS
Package ID Status date Status
NEA-1643/01 30-AUG-2002 Tested at NEADB
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10. REFERENCES

- J. Cetnar, W. Gudowski and J. Wallenius, "MONTE-CARLO CONTINUOUS ENERGY BURNUP (MCB1C) - THE CODE DESCRIPTION, METHODS AND BENCHMARKS" in preparation for NSE.

- J. Cetnar, W. Gudowski and J. Wallenius, "MCB: A continuous energy Monte Carlo Burnup simulation code",  In "Actinide and Fission Product Partitioning and Transmutation", EUR 18898 EN, OECD/NEA (1999) 523.

Users are also kindly requested to check and update the references on MCB1C web-page http://www.neutron.kth.se/mcb
NEA-1643/01, included references:
- J. Cetnar, W. Gudowski, J. Wallenius and K. Tucek:
Simulation of Nuclide Transmutations with Monte-Carlo Continuous
Energy Burnup Code (MCB1C)
- W. Gudowski et al.:
IAEA Benchmark on Accelerator-Driven Systems
- J. Cetnar, W. Gudowski, J. Wallenius:
User Manual for Monte-Carlo Continuous Energy Burnup (MCB) Code
Version 1C
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11. HARDWARE REQUIREMENTS

MCB is operable on workstations or PC's running Unix or Linux.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1643/01 FORTRAN-77, C-LANGUAGE
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13. SOFTWARE REQUIREMENTS

Compilation of MCB requires both FORTRAN77 (f77 or g77) and ANSI C (cc  or gcc) compilers. PVM is required for multiprocessing on a cluster of workstations and can be downloaded from www.netlib.org. Scripts are provided for installation on both LINUX and Unix systems.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

   Department of Nuclear and Reactor Physics
   Royal Institute of Technology
   100 44 Stockholm
   Sweden
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16. MATERIAL AVAILABLE
NEA-1643/01
mcb.tar.gz    The MCB code (compressed tar file)
bplib.tar.gz    The burnup library - BPLIB (compressed tar file)
eaf.mcbxl.tar.gz    xsdir for EAF (compressed tar file)
eaf99.A.tar.gz    Dosimetry cross sections library EAF99
Install     Installation script for MCB
InstEaf    Installation script for EAF99 cross sections library
MakePatch    Script for making MCB compilation script
Manual_MCB.pdf    User manual (PDF format)
MCB1C_um.doc   Usernal manual (Word format)
Readme    Readme for MCB1C installation
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • J. Gamma Heating and Shield Design

Keywords: Monte Carlo method, burnup, criticality, flux distribution, neutronics, reaction rates, shielding.