NUCLEAR DATA SERVICES
DOCUMENTATION SERIES OF THE IAEA NUCLEAR DATA SECTION
Rev. 1, July 1995
Summary description by H.D. Lemmel
|The MENDL-2 nuclear data library contains for 505 stable and unstable target nuclides production cross-sections for the formation of radioactive product nuclides for incident neutrons with energies up to 100 MeV. The nuclides included cover the range from 13-Al-26 to 84-Po-210 with half-lives larger than one day. The data library is available from the IAEA Nuclear Data Section, costfree, upon request.|
Nuclear Data Section
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fax: (43-1) 20607
cable: INATOM VIENNA
telex: 1-12645 atom a
telephone: (43-1) 2060-21710
|online:||TELNET or FTP: IAEAND.IAEA.ORG|
username: IAEANDS for interactive Nuclear Data Information System
username: NDSOPEN for FTP file transfer
The IAEA-NDS-docurnents should not be considered as publications or reports. When a nuclear data library is sent out by the IAEA Nuclear Data Section, it will be accompanied by an IAEA-NDS-document which should give the data user all necessary information on contents, format and origin of the data library.
IAEA-NDS-documents are updated whenever there is additional information of relevance to the users of the data library.
For citations care should be taken that credit is given to the author of the data library and/or to the data center which issued the data library. The editor of the IAEA-NDS-document is usually not the author of the data library.
Neither the originator of the data libraries nor the IAEA assume any liability for their correctness or for any damages resulting from their use.
This data library should be cited as follows:
This data library is described in the following references:
A brief description of MENDL-1 which was distributed during the International Conference on Nuclear Data for Science and Technology, Gatlinburg, USA, May 1994, is attached.
The authors are from two institutes in Obninsk, Russia, i.e. Institut Atomnoi Energetiki (Nuclear Power Engineering, INPE) and the Fiziko-Energeticheskij Institut, FEI (Physics and Power Engineering, IPPE).
|Contents:||Neutron cross-sections for neutrons up to 100 MeV.|
|Format:||The data are given in an ENDF similar format, but with a free
choice of MT numbers to identify the different reactions; these are
explained in each file.|
ENDF plotting codes will not function.
|Libraries:||There is an index file ("catalogue") listing the 57 500 reactions included, and a data file.|
Authors: Yu.N. Shubin, A.Yu. Konobeyev1, Yu.A. Korovin1, V.P. Lunev, V.S. Masterov
Institute of Physics and Power Engineering (IPPE), Obninsk 249020,
1Institute of Nuclear Power Production (INPP), Obninsk 249020, Russia
MENDL (Medium Energy Nuclear Data Library) has been elaborated in Theoretical Division of Institute of Physics and Power Engineering. The library is intended for activation and transmutation study for materials irradiated by intermediate energies particles.
MENDL contains neutron induced reaction cross-sections at energies 0-100 MeV for stable nuclei and unstable nuclei with half-life more than 1 day and atomic number from 13 up to 83. The library includes cross-sections for 497 nuclei and 31704 reactions.
The method to obtain cross-sections was based on geometry dependent hybrid exciton model  and Weisskopf-Ewing model. The multiple precompound nucleon emission was calculated using approach  with some corrections. The alpha-particle precompound emission was described in the framework of coalescence pick-up model  combined directly with hybrid exciton model. Exciton state density was defined according to the Ericson formula taking into account the Pauli principle and pairing of nuclear levels. To calculate intranuclear transition rate nucleon-nucleon interaction cross-sections corrected for the Pauli principle were used.
Level density calculations were performed according to Ignatyuk et al.  taking into account the shell effects. The individual level density parameters were used for all nuclei formed in the evaporation cascade.
Total reachon cross-section and inverse cross-sections were calculated using optical model.
Correction of calculated cross-sections was performed for some reaction channels to achieve the agreement with available experimental data. The calculated cross-sections were corrected to reproduce full experimental excitation functions or were normalized to known cross-section values at 14.5 MeV. For stable nuclei the experimental cross-sections and cross-sections obtained from systematics at 14.5 MeV presented in  were used.
Briefly this version of MENDL library is described in Ref. .
The MENDL catalogue presented here includes the following information.
The Iine beginning with symbol " * " contains the characteristics of target nucleus with indication atomic number, name of element, atomic mass number, half-life and total number of reactions considered nucleus and contained in MENDL files.
The line with reaction description indicates:
13-Al-26 (N,X) 11-Na-22 2.60E+OOY 62 -9.450E+00 Original
13-Al-26 : target nucleus is aluminium isotope with A=26 (N,X) : sum of(n,n alpha) and (n,3n2p) reaction cross-sections 11-Na-22 : product nucleus is sodium isotope with A=22 2.6OE+00Y : half-live of 22Na is equal 2.6 year 62 : the number of energy points for this reaction is equal to 62 -9.450E+00: Q-value for (n,n alpha) reaction Original : reaction cross-section has been obtained by authors
Target Reaction Product Half-live Points Q value Comments *13-Al-26 unstable 7.205E+05Y 57 reactions 13-Al-26 (N,2N) 13-Al-25 7.18E+OOS 65 -1.137E+01 Original 13-Al-26 (N,3N) 13-Al-24 2.07E+OOS 45 -2.830E+01 Original 13-AI-26 (N,4N) 13-Al-23 4.70E-OlS 25 -4.319E+01 Original 13-Al-26 (N,P) 12-Mg-26 stable 77 4.786E+00 Original 13-Al-26 (N,X) 12-Mg-25 stable 67 -6.306E+00 Original 13-Al-26 (N,X) 12-Mg-24 stable 60 -1.364E+01 Original 13-Al-26 (N,X) 12-Mg-23 1.13E+OlS 41 -3.017E+01 Original 13-Al-26 (N,X) 12-Mg-22 3.86E+OlS 24 -4.332E+01 Original 13-Al-26 (N,X) 12-Mg-21 1.23E-OlS 7 -6.238E+01 Original 13-Al-26 (N,2P) 11-Na-25 5.96E+OlS 64 -9.358E+00 Original 13-Al-26 (N,X) 11-Na-24 1.50E+OlH 54 -1.837E+01 Original 13-Al-26 (N,X) 11-Na-23 stable 77 2.968E+00 Original 13-Al-26 (N,X) 11-Na-22 2.60E+OOY 62 -9.450E+00 Original 13-Al-26 (N,X) 11-Na-21 2.25E+OlS 50 -2.052E+01 Original (see full contents in a special file) *13-AI-26 13 24 99 0*MENDL92 * 0 45-2.82976E+01 31.000 0.0 32.000 3.55E-03 33.000 1.55E-02 34.000 5.26E-02 35.000 1.10E-01 36.000 1.50E-01 37.000 2.50E-01 38.000 3.51E-01 39.000 4.88E-01 40.000 6.25E-01 41.000 6.79E-01 42.000 7.62E-01 43.000 8.35E-01 44.000 9.39E-01 45.000 1.01E+00 46.000 1.04E+00 47.000 1.07E+00 48.000 1.14E+00 49.000 1.20E+00 50.000 1.21E+00 52.000 1.29E+00 54.000 1.27E+00 56.000 1.28E+00 58.000 1.28E+00 60.000 1.28E+00 62.000 1.20E+00 64.000 1.16E+00 66.000 1.12E+00 68.000 1.13E+00 70.000 1.04E+00 72.000 9.94E-01 74.000 9.46E-01 76.000 9.36E-01 78.000 8.67E-01 80.000 8.66E-01 82.000 8.56E-01 84.000 7.96E-01 86.000 7.65E-01 88.000 7.37E-01 90.000 7.36E-01 92.000 6.87E-01 94.000 6.88E-01 96.000 6.64E-01 98.000 6.69E-01 100.00 6.28E-01 *13-Al-26 13 23 99 0*MENDL92* 0 25-4.31910E+01 52.000 0.0 54.000 1.44E-03 56.000 2.45E-03 58.000 5.36E-03 60.000 8.79E-03 62.000 1.04E-02 64.000 1.24E-02 66.000 1.41E-02 68.000 1.54E-02 70.000 1.59E-02 72.000 1.66E-02 74.000 1.78E-02 76.000 1.82E-02 78.000 1.82E-02 80.000 1.78E-02 82.000 1.94E-02 84.000 1.94E-02 86.000 2.05E-02 88.000 2.15E-02 90.000 2.34E-02 9.000 2.41E-02 94.000 2.42E-02 96.000 2.39E-02 98.000 2.53E-02 100.00 2.59E-02
Nuclide Ref. Comments 27-Al 1,2 45-Sc 3 55-Mn 1 56-Fe 4,5 59-Co 1,5 68-Zn 3 75-As 6 88-Sr 7 Quoted as in  89-Y 8 90-Zr 9 96-Mo 10 127-I 11-17 (p,3n),(p,5n):[11,17]; (p,6n):[13,14]; (p,7n):[14,16]; (p,3np):. Data [11,12,15] quoted as in  141-Pr 18 202-Hg 19 209-Bi 20