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

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-MCB-ENDF/B6.8.

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:

DVD version, contains NEA-1669/01 and NEA-1669/02

4. METHODS

The library was generated using the NJOY processing code. An example of the input data is provided.

6. TYPICAL RUNNING TIME

The ASCII-to-binary conversion can generally be accomplished within a few seconds, even for the large data files.

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.

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).

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.

15. NAME AND ESTABLISHMENT OF AUTHORS

       Department of Nuclear and Reactor Physics
       Royal Institute of Technology
       100 44 Stockholm
       Sweden

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

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

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