NEA-0827 ZZ-DOSCROS84.
ZZ DOSCROS, Neutron Cross-Section Library for Spectra Unfolding and Integral Parameter Evaluation
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| 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 |
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3. DESCRIPTION OF PROBLEM OR FUNCTION
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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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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.
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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.
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.
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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)
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NEA-0827/04
| File name | File description | Records |
|---|---|---|
| NEA0827_04.001 | THIS INFORMATION FILE | 53 |
| NEA0827_04.002 | DOSCROS84 CROSS SECTION LIBRARY | 9770 |
Keywords: ENDF/B, cross sections, data, multigroup, neutron spectra.