7.800000+4 1.934140+2 0 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 25 1
78-Pt- 0 NEA,LLNL EVAL-OCT83 HOWERTON R.J.
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 7800
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 + Corrections **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
1.000000+4 ==> 1.000000+5
DATA TAKEN FROM :- ENDL-78 (REVISION L)
Isotropic MF-4 16,17 and 91 added
******************************************************************
NOTE:
CONVERSION FROM ENDF-4 to ENDF-6 FORMAT AT NEA DATA BANK
ON 08/04/98 USING EB4TOEB5 AND EB5TOEB6
REFERENCE:
FOR A COMPLETE DISCUSSION OF THE EVALUATION SEE UCRL 50400 VOL 15
1 451 30
Back