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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. Only liaison officers are authorised to submit online requests. Rules for requesters 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 item found

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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.