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NEA-1669 ZZ-MCB-ENDF/B-6.8.

ZZ MCB-ENDF/B6.8, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K.

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-MCB-ENDF/B6.8.
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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-MCB-ENDF/B-6.8 NEA-1669/01 Tested 30-AUG-2002
ZZ-MCB-ENDF/B-6.8 NEA-1669/02 Tested 30-AUG-2002
ZZ-MCB-ENDF/B-6.8 NEA-1669/03 Tested 20-DEC-2004

Machines used:

Package ID Orig. computer Test computer
NEA-1669/01 Linux-based PC,UNIX W.S. Linux-based PC
NEA-1669/02 Linux-based PC,UNIX W.S. Linux-based PC
NEA-1669/03 Linux-based PC,UNIX W.S. Linux-based PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

MCB-ENDF/B6.8 is a continuous-energy cross section libraries in ACE format suitable for the MCB-1C and MCNP codes. Libraries for various materials were generated at six different temperatures, and cover
the energy range up to 150 MeV.
FORMAT: ACE
NUMBER OF GROUPS: Continuous energy
NUCLIDES: Library includes elements with the following atomic numbers:
Z= 1-9, 11-17, 19-29, 31-68, 71-75, 77, 79, 82-83, 90-99, (i.e.: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Hf, Ta, W, Re, Ir, Au, Pb, Bi, Th, Pa, U, Np, Pu, Am, Cm, Bk, Cf, Es).
TEMPERATURES: 300 K, 600 K, 900 K, 1200 K, 1500 K, and 1800 K.
ORIGIN: ENDF/B-6.8
WEIGHTING SPECTRUM:
NEA-1669/03
DVD version, contains NEA-1669/01 and NEA-1669/02
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4. METHODS

The library was generated using the NJOY processing code. An example of the input data is provided.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

The ASCII-to-binary conversion can generally be accomplished within a few seconds, even for the large data files.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

MAKSF, which is distributed with CCC-700/MCNP4C, can be used to convert MCNP Type 1 data to Type 2 (binary). For use with the code MCB-1C the MAKXSF installation must be slightly modified.
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9. STATUS
Package ID Status date Status
NEA-1669/01 30-AUG-2002 Tested at NEADB
NEA-1669/02 30-AUG-2002 Tested at NEADB
NEA-1669/03 20-DEC-2004 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.

- J. F. Briesmeister, Ed.
"MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709-M (April 2000).
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11. HARDWARE REQUIREMENTS

ASCII card images; Unix workstation. The library distribution was prepared on a LINUX system. On a Windows-based PC, one may use utilities such as WinZip(R) to unzip and extract the library files.
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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

       Department of Nuclear and Reactor Physics
       Royal Institute of Technology
       100 44 Stockholm
       Sweden
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16. MATERIAL AVAILABLE
NEA-1669/01
InstEndf   Installs ENDF/B-6.8 cross section library
endf.mcbxl.tar.gz    ENDF/B-6.8 xsdir
endfb6.8.A1.tar.gz    Transport cross section library based on ENDF/B-6.8
Readme.Endfb6.8  ENDF/B-6.8 cross section library installation dedicated for MCB

NEA-1669/02
endfb6.8.A2.tar.gz    Transport cross section library based on ENDF/B-6.8

NEA-1669/03
Readme.Endfb6.8    Original information file
InstEndf-l  Installation procedure for independent library installation
(outside MCB system)
ENDFB6.8 cross section data library (two files per temperature)
XSDIR files XSDIR file for LINUX and UNIX operating systems
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17. CATEGORIES
  • Z. Data.

Keywords: Monte Carlo method, cross sections, data library, fission products, neutrons, reaction.