4.610200+4 1.010300+2 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 80 1
46-Pd-102 NEA RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 4625
-----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=9379). *
******************************************************************
* 11-AUG-86: RESONANCE PARAMETER SECTION UPDATED USING DATA *
* FROM THE 4TH ED. OF BNL-325. *
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
******************************************************************
****************************************************************
* *
* MODIFICATIONS FOR JEF-2 46-PD-102 *
* *
****************************************************************
* *
* COOPERATION ECN-PETTEN AND NEA DATA BANK *
* H.A.J. VAN DER KAMP - ECN *
* H.GRUPPELAAR - ECN *
* I.FOREST - NEADB *
* C.NORDBORG - NEADB *
* *
****************************************************************
* RESOLVED RESONANCE REGION: *
****************************************************************
* *
* RESOLVED RESONANCE PARAMETERS WERE REPLACED BY DATA FROM *
* MOST RECENT BROOKHAVEN COMPILATION(MU81). *
* *
* EL=10-5 EV, EH=0.3972 KEV. *
* *
****************************************************************
* THERMAL VALUES (2200M/S): *
****************************************************************
* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 5.68032 B *
* MT=102 SIGMA = 3.36437 B *
* MT=102 RESONANCE INTEGRAL = 13.2171 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = NOT AVAILABLE *
* MT=102 SIGMA = 3.4 +- 0.3 B *
* MT=102 RESONANCE INTEGRAL = NOT AVAILABLE *
* *
****************************************************************
* REFERENCES: *
****************************************************************
* *
* MU81: MUGHABGHAB,S.F., M.DIVADEENAM, N.E.HOLDEN *
* NEUTRON CROSS SECTIONS VOLUME 1 *
* NEUTRON RESONANCE PARAMETERS AND THERMAL CROSS *
* SECTIONS, PART A, Z=1-60, ACADEMIC PRESS 1981 *
* *
****************************************************************
HEDL EVAL-FEB80 F.M.MANN
DIST-JUL80 800625
MF=2, MT=251 SCATTERING RADIUS ONLY
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 85
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