3.407400+4 7.328700+1 1 0 2 0
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 35 1
34-Se- 74 NEA RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 3425
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
******************************************************************
* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=9089). *
******************************************************************
* 15-JAN-85: RESONANCE PARAM. CHANGED TO ORIGINAL SINGLE-LEVEL.
* 20-APR-89: RESONANCE PARAM. CHANGED TO MULTI-LEVEL FORMULA
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
******************************************************************
HEDL EVAL-FEB80 F.M.MANN
DIST-JUL80 800625
MF=2, MT=251 FROM BNL-325(1973)
MF=3 CROSS SECTIONS ARE FROM HAUSER-FESHBACH CALCULATIONS
USING THE MOLDAUER POTENTIAL
LOW ENERGY DATA DETERMINED FROM THERMAL CROSS SECTION
USING A 1.0/V TAIL
MF=4 ISOTROPIC ANGULAR DISTRIBUTIONS
MF=5 EVAPORATION TEMPERATURES FROM 3.2*SQRT(E/AWR)
1 451 40
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