IAEA1275 ZZ-ACTIV-87.
ZZ ACTIV-87, Fast Neutron Activation Cross-Section
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-ACTIV-87 | IAEA1275/01 | Tested | 18-AUG-1995 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| IAEA1275/01 | Many Computers | DEC VAX 6000 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
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ACTIV - 87
==========
FORMAT: ENDF 5 format
NUMBER OF GROUPS: Energies from threshold to 20 MeV.
NUCLIDES: Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, Ge, As, Se, Br, Rb, Sr, Y, Zr, Nb, Mo, Tc, Rh, Ag, Cd, In, Sn, Sb, I, Cs, Ce, Pr, Nd, Au, Hg, Tl, Pb, Bi, Th, U, Sm, Ho, Tm, Lu, Hf, Ta, W, Re.
ORIGIN: BOSPOR, ENDL, ENDF/B-V, IRDF-82 and individual evaluation carried out under various IAEA research contracts.
WEIGHTING SPECTRUM: --
ACTIV - FUS / INT
=================
FORMAT: ENDF 6 format
NUMBER OF GROUPS: 372 neutron induced reactions for neutron ener- gies from threshold to 20 MeV.
NUCLIDES: B, C, N, O, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Zr, Nb, Mo, Rh, Pd, Ag, Cd, Sn, Sb, Te, Cs, Ba, La, Ce, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: REAC-2,REAC-ECN, BOSPOR-86, SINCROSACT, ADL-90, ENDF/B-VI, JENDL-3 and BROND.
WEIGHTING SPECTRUM: --
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
A compilation of fast neutron induced activation reaction cross sections used in neutron activation analysis applications. The data are written in ENDF/B-5 format and cover energies from the threshold to 20 MeV. The file of selected reactions contains 206 evaluated cross section curves of the (n.2n), (n,p), and (n,alpha) reactions which lead to radioactive products.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
ACTIV - 87
==========
FORMAT: ENDF 5 format
NUMBER OF GROUPS: Energies from threshold to 20 MeV.
NUCLIDES: Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, Ge, As, Se, Br, Rb, Sr, Y, Zr, Nb, Mo, Tc, Rh, Ag, Cd, In, Sn, Sb, I, Cs, Ce, Pr, Nd, Au, Hg, Tl, Pb, Bi, Th, U, Sm, Ho, Tm, Lu, Hf, Ta, W, Re.
ORIGIN: BOSPOR, ENDL, ENDF/B-V, IRDF-82 and individual evaluation carried out under various IAEA research contracts.
WEIGHTING SPECTRUM: --
ACTIV - FUS / INT
=================
FORMAT: ENDF 6 format
NUMBER OF GROUPS: 372 neutron induced reactions for neutron ener- gies from threshold to 20 MeV.
NUCLIDES: B, C, N, O, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Zr, Nb, Mo, Rh, Pd, Ag, Cd, Sn, Sb, Te, Cs, Ba, La, Ce, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: REAC-2,REAC-ECN, BOSPOR-86, SINCROSACT, ADL-90, ENDF/B-VI, JENDL-3 and BROND.
WEIGHTING SPECTRUM: --
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
A compilation of fast neutron induced activation reaction cross sections used in neutron activation analysis applications. The data are written in ENDF/B-5 format and cover energies from the threshold to 20 MeV. The file of selected reactions contains 206 evaluated cross section curves of the (n.2n), (n,p), and (n,alpha) reactions which lead to radioactive products.
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IAEA1275/01, included references:
- V.N. Manokhin et al:ACTIV87 - Fast Neutron Activation Cross Section File 1987
IAEA-NDS-96 Rev. 0 (October 1989).
- A.B. Pashchenko:
ACTV-FUS/INT - The International Library of Neutron Activation
Cross-Section Data for Fusion Reactor Application (FENDL
Activation Sublibrary)
IAEA-NDS-148 Rev. 0 (November 1991).
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IAEA1275/01
| File name | File description | Records |
|---|---|---|
| IAEA1275_01.001 | Information file of the package ZZ-ACTIV-87 | 103 |
| IAEA1275_01.002 | FENDL Activation Sublibrary (ENDF/B-VI) | 254231 |
| IAEA1275_01.003 | ACTIV87 library (ENDF/B-V) | 13887 |
Keywords: activation analysis, cross sections, data library, fast neutrons, neutron cross sections, neutron reactions.