2.300000+4 5.050400+1 1 0 2 1
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 56 1
23-V - 0 ECN EVAL-OCT91 GRUPPELAAR,VD.KAMP,KOPECKY,NIEROP
EFF-DOC DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 2300
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 *************************
DATA TAKEN FROM :- EFF-3.0 (DIST-OCT91 REV2-OCT91)
******************************************************************
* *
* EEEEEEEE FFFFFFFF FFFFFFFF 3333333 000 *
* E F F 3 0 0 *
* E F F 3 0 0 *
* EEEEEE FFFFFF FFFFFF 3333333 * 0 0 *
* E F F 3 0 0 *
* E F F 3 0 0 *
* EEEEEEEE F F 3333333 000 *
* *
******************************************************************
EUROPEAN FUSION FILE VERSION 3.0
--------------------------------
The European Fusion File is a project of various European
laboratories and is sponsored by the European Fusion Programme of
the European Union.
The data file EFF-3.0 is maintained at ECN-Petten. Contact:
Dr. H. Gruppelaar
ECN Nuclear Energy
Netherlands Energy Research Foundation ECN
P.O. Box 1
1755 ZG Petten
The Netherlands
******************************************************************
** This evaluation has been selected from ENDF/B-6 library
** by ENEA-BOLOGNA
Revision 3 by M.Herman, F.Fabbri and G.Reffo at ENEA-Bologna
feb. 1995
Double differential cross sections for MT=16,22,28,91,103,107
(including recoil nuclei and gamma emission) added based on the
compound nucleus and preequilibrium calculations performed with
the ida code system.
Angular distributions (MF4) for discrete levels MT=51-63 taken
from JENDL-3
1 451 61
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