1. NAME AND TITLE
ACTIV87: Fast Neutron Activation Cross Section File.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
None is provided with the package. However, PSR-333/CHENDF 6.8 package can be used to access the data.
International Atomic Energy Agency, Vienna, Austria.
4. HISTORICAL BACKGROUND AND INFORMATION
ACTIV87 is a compilation of fast neutron induced activation reaction cross-sections. The compilation covers energies from threshold to 20 MeV and is based on evaluated data taken from other evaluated data libraries and individual evaluations. The majority of these evaluations were performed by using available experimental data. The aforementioned available experimental data were used in the selection of needed parameters for theoretical computations and for normalizing the results of such computations. Theoretical calculations were also used for interpolation and extrapolation of experimental cross-section data.
All of the evaluated data curves were compared with experimental data that had been reported over the four year period preceding 1987. Only those cross-sections not in contradiction with experimental data that was current in 1987 were retained in the activation file, ACTIV87. In cases of several conflicting evaluations, that evaluation was chosen which best corresponded to the experimental data. A few evaluated curves were renormalized in accordance with the results of the latest precision measurements.
5. APPLICATION OF THE DATA
6. SOURCE AND SCOPE OF DATA
The following libraries and individual files of evaluated neutron cross-section data were used for the selection of the activation cross-sections: the BOSPOR Library, the Activation File of the Evaluated Nuclear Data Library, the Evaluated Neutron Data File (ENDF/B-V) Activation File, the International Reactor Dosimetry File (IRDF-82), and individual evaluations carried out under various IAEA research contracts.
The file of selected reactions contains 206 evaluated cross-section curves of the (n,2n), (n,p) and (n,a) reactions which lead to radioactive products and may be used in many practical applications of neutron activation analysis. Some competing activation reactions, usually with low cross-section values, are given for completeness.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS
No retrieval program is included. However, the CHECKR utility of CHENDF 6.8 was used to check ACTIV87 at RSIC, and the files do not consistently conform to ENDF formats.
8. DATA FORMAT
The data are in ENDF-5 format. However, the arrangement of the evaluations does not strictly conform to the rules. This is related to CHECKR finding problems like the same MAT number appearing twice, giving data for two reactions (e.g. (n,p) and (n,2n)) separately.
9. COMPUTER SOFTWARE REQUIREMENTS
A retrieval code capable of reading files in ENDF-5 format.
V. N. Manokhin, A. B. Pashchenko, V. I. Plyaskin, V. M. Bychkov, V. G. Pronyaev, "ACTIV87, Fast Neutron Activation Cross Section File" IAEA-NDS-96 (October 1989).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and library on one DS/HD 5.25-inch (1.2MB) diskette in DOS format.
12. DATE OF ABSTRACT
KEYWORDS: EVALUATED NEUTRON CROSS SECTIONS; REACTION CROSS SECTIONS