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46-Pd-102 NEA RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP DIST-JAN09 20090105 ----JEFF-311 MATERIAL 4625 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** 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)Back |