Computer Programs
NEA-1655 ZZ-MCB63NEA.BOLIB.
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NEA-1655 ZZ-MCB63NEA.BOLIB.

ZZ MCB63NEA.BOLIB, MCNP Cross Section Library Based on ENDF/B-VI Release 3

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-MCB63NEA.BOLIB
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-MCB63NEA.BOLIB NEA-1655/01 Tested 04-OCT-2001

Machines used:

Package ID Orig. computer Test computer
NEA-1655/01 Many Computers PC Pentium III
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Continuous energy cross-section data library for the Monte Carlo program MCNP based on the ENDF/B-VI Release 3 evaluated nuclear data library (ACE format).
FORMAT: ACE
NUMBER OF GROUPS: Continuous energy
NUCLIDES (107): H-1, H-2, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, N-14, N-15, O-16, O-17, Na-23, Mg-nat, Al-27, Si-nat, Cl-nat, Ti-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Zr-90, Zr-91, Zr-92, Zr-94, Zr-96, Zr-nat, Nb-93, Mo-94, Mo-95, Mo-96, Mo-97, Mo-nat, Tc-99, Ru-101, Ru-102, Ru-104, Rh-103, Pd-105, Pd-107, Ag-109, I-129, Xe-131, Cs-133, Pr-141, Nd-143, Nd-145, Pm-147, Sm-147, Sm-149, Sm-150, Sm-151, Sm-152, Eu-153, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Hf-nat, Pb-206, Pb-207, Pb-208, Bi-209, Th-232,U-233, U-234, U-235, U-236, U-238, Np-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-242m, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248.
TEMPERATURES:300, 500, 560, 760, 800, 1000, 1500, and 2200 deg.K
THERMAL SCATTERING (for diverse temperatures)
H in CH2 (polyethylene)
H in H2O (light water)
D in D2O (heavy water)
C        (graphite)
Be       (beryllium metal)
DOSIMETRY CROSS-SECTION: 16-S-32, 48-Cd-0, 79-Au-197
ORIGIN: ENDF/B-VI Release 3, IRDF-90 Version 2
WEIGHTING SPECTRUM:
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4. METHODS

This library was generated with the NJOY-94.66 nuclear data processing system.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

PRPR: Fortran 77 pre-processor source.
MAKXSF: Prepares the MCNP Cross-Section Libraries.
These programs are distributed with the Monte Carlo code package CCC-0660/MCNP-4B.
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9. STATUS
Package ID Status date Status
NEA-1655/01 04-OCT-2001 Screened
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10. REFERENCES

- J. F. Briesmeister Editor, MCNP-A General Monte Carlo N-Particle Transport Code, Version 4B, LA-12625-M, Version 4B, March 1997.
- R.E. MacFarlane, D.W. Muir, The NJOY Nuclear Data Processing System, Version 94.66, Los Alamos National Laboratory (USA), December 19, 1996.
- R. Orsi, M. Pescarini, A.I. Blokhin, MCB6.BOLIB AN ENDF/B-VI LIBRARY FOR THE MCNP MONTE CARLO CODE, JEF/DOC-766, JEFF Working Group Meeting on Benchmark Testing, Data Processing and Evaluations, NEA Data Bank, Issy-Les-Moulineaux, September 17th - 18th , 1998.
- R. Orsi, M. Pescarini, A.I. Blokhin, MCB6.BOLIB - AN ENDF/B-VI RELEASE 3 CROSS SECTION LIBRARY FOR THE MCNP MONTE CARLO CODE, JEF/DOC-779, JEFF Working Group Meeting on Benchmark Testing, Data Processing and Evaluations, NEA Data Bank, Issy-Les-Moulineaux, April 12th - 14th , 1999. ENEA, ERG-SIEC, Internal Report KT-SCG-00004.
- N.P. Kocherov, P.K. McLaughlin, THE INTERNATIONAL REACTOR DOSIMETRY FILE (IRDF-90 Version 2), IAEA-NDS-141 Rev. 2, October 1993.
NEA-1655/01, included references:
-R.Orsi, M.Pescarini, A.I.Blokhin and V.Sinitsa;
MCB63NEA.BOLIB
An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code
ENEA - KT-SCG-00014 (June 28, 2001)
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11. HARDWARE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

   R. Orsi, M. Pescarini, A. I. Blokhin(*), V. Sinitsa(*)
   ENEA - Centro Ricerche
   'E. Clementel'
   Via Martiri di Monte Sole, 4
   I-40129 BOLOGNA
   ITALY
(*) on leave from the Institute of Physics and Power Engineering, Obninsk, Russian Federation
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16. MATERIAL AVAILABLE
NEA-1655/01
Pointwise cross sections in ACE format for transport calculations
Thermal scattering data for various important moderator materials
Some dosimeter response functions
NJOY input jobs
107 isotopes/natural elements processed for up to 8 temperatures
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17. CATEGORIES
  • Z. Data.

Keywords: Monte Carlo method, cross sections, energy.