last modified: 07-SEP-1987 | catalog | categories | new | search |

NEA-0827 ZZ-DOSCROS84.

ZZ DOSCROS, Neutron Cross-Section Library for Spectra Unfolding and Integral Parameter Evaluation

top ]
1. NAME OR DESIGNATION OF PROGRAM:  ZZ-DOSCROS81.
top ]
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-DOSCROS84 NEA-0827/04 Tested 07-SEP-1987

Machines used:

Package ID Orig. computer Test computer
NEA-0827/04 CDC 7600,VAX under VMS CDC 7600,VAX under VMS
top ]
3. DESCRIPTION OF PROBLEM OR FUNCTION


%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

  FORMAT: SAND-II

  NUMBER OF GROUPS: 640 fine group cross section values

NUCLIDES: Li, B, F, Na, Mg, Al, S, Sc, Ti, Cr, Mn, Fe, Co, Ni, Cu,  Zn, As, Br, Nb, Mo, Rh, Pd, Ag, In, Sb, I, Cs, La, Eu, Sm, Dy, Lu, Ta, W, Re, Au, Th, U, Np, Pu.

  ORIGIN: ENDF/B-V mainly, ENDF/B-IV, INDL/V

  WEIGHTING SPECTRUM: --

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

   This library forms in combination with the DAMSIG81 library a
convenient source of evaluated energy dependent cross section sets which may be used in the determination of neutron spectra by means of adjustment (or unfolding) procedures or which can be used for the determination of integral parameters (such as damage-to-activation ratio) useful in characterising the neutron spectra. The energy dependent fine group cross section data are presented in  a 640 group structure of the SAND-II type.
This group structure has 45 energy groups per energy decade below 1 MeV and a group width of 100 KeV above 1 MeV.
The total energy span of this group structure is from 10**(-10) MeV to 20 MeV.
The library has the SAND-II format, which implies that a special part of the library has to contain cover cross section data sets. These cross section data sets are required in the SAND-II program for taking into account the influence of special detector surroun dings which may be used during an irradiation.
top ]
4. METHOD OF SOLUTION

The selection of the reactions from the evalua- ted nuclear data libraries was determined by various properties of the reactions for neutron metrology. For this reason all the well- known reactions of the ENDF/B-V dosimetry file are included but these data are supplemented with cross section sets for less well known metrology reactions which may become of interest.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
top ]
6. TYPICAL RUNNING TIME:
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS:
top ]
9. STATUS
Package ID Status date Status
NEA-0827/04 07-SEP-1987 Tested at NEADB
top ]
10. REFERENCES:
NEA-0827/04, included references:
- W. L. Zijp, H. J. Nolthenius and G.C.H.M. Verhaag:
  Cross-Section Library DOSCROS84 (in a 640 group structure of the
  SAND-2 type).  ECN-160  (October 1984)
top ]
11. MACHINE REQUIREMENTS:
top ]
12. PROGRAMMING LANGUAGE(S) USED

No item found

top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

Willem L. Zijp, Henk J. Nolthenius,
Henk Ch. Rieffe
Netherlands Energy Research Foundation
ECCN, Petten, Netherlands
top ]
16. MATERIAL AVAILABLE
NEA-0827/04
File name File description Records
NEA0827_04.001 THIS INFORMATION FILE 53
NEA0827_04.002 DOSCROS84 CROSS SECTION LIBRARY 9770
top ]
17. CATEGORIES
  • O. Experimental Data Processing
  • Z. Data.

Keywords: ENDF/B, cross sections, data, multigroup, neutron spectra.