Eu-155 (neutron) revision 1 from tape120 1 0 0 0 6.315500+4 1.535920+2 1 0 0 26337 1451 1 0.000000+0 1.000000+0 0 0 0 66337 1451 2 1.000000+0 0.000000+0 0 0 10 66337 1451 3 0.000000+0 0.000000+0 0 0 99 456337 1451 4 63-EU-155 ORNL, HEDL EVAL-DEC88 WRIGHT,PRINCE,SCHENTER 6337 1451 5 DIST-SEP91 REV1-AUG91 910806 6337 1451 6 ----ENDF/B-VI MATERIAL 6337 REVISION 1 6337 1451 7 -----INCIDENT NEUTRON DATA 6337 1451 8 ------ENDF-6 FORMAT 6337 1451 9 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 6337 1451 10 * * * * * * *6337 1451 11 ORNL EVAL-DEC88 R. Q. WRIGHT 6337 1451 12 INEL EVAL-DEC79 PRINCE, SCHENTER 6337 1451 13 BNL,HEDL EVAL-OCT74 A.PRINCE AND R.E. SCHENTER 6337 1451 14 *****************************************************************6337 1451 15 Revision-1 has corrected the illegal J-values in file 2. 6337 1451 16 *****************************************************************6337 1451 17 THE ENDF/B-V EU-155 EVALUATION, MAT 9832, HAS BEEN REVISED BELOW 6337 1451 18 35 EV. THE REVISED EVALUATION HAS BEEN ASSIGNED MATNO 6337 6337 1451 19 IN ORDER TO DIFFERENTIATE IT FROM THE ORIGINAL EVALUATION. 6337 1451 20 IN THE REVISED EVALUATION, RESOLVED RESONANCE PARAMETERS ARE USED6337 1451 21 TO DEFINE THE TOTAL, ELASTIC, AND CAPTURE CROSS SECTIONS BELOW 6337 1451 22 35 EV. ABOVE 35 EV THE EVALUATION IS UNCHANGED FROM ENDF/B-V. 6337 1451 23 THE RESOLVED RESONANCE PARAMETERS ARE TAKEN FROM REF. (1). 6337 1451 24 THE MLBW (LRF=2) REPRESENTATION WAS USED WITH THE SMOOTH BACK- 6337 1451 25 GROUND SET TO ZERO IN THE RESONANCE REGION. 6337 1451 26 THE LARGEST CONTRIBUTION TO THE THERMAL CAPTURE CROSS SECTION 6337 1451 27 AND TO THE CAPTURE RESONANCE INTEGRAL IS FROM THE FIRST RESONANCE6337 1451 28 AT 0.603 EV WHICH HAS A PEAK CAPTURE CROSS SECTION (AT 300 K) OF 6337 1451 29 ABOUT 102,000 BARNS. THE THERMAL CAPTURE CROSS SECTION IS 6337 1451 30 SLIGHTLY LOWER THAN ENDF/B-V BUT THE CAPTURE RESONANCE INTEGRAL 6337 1451 31 IS HIGHER THAN THE ENDF/B-V VALUE BY ABOUT A FACTOR OF 12. 6337 1451 32 6337 1451 33 2200 M/S CAPTURE CROSS SECTION, BARNS. 6337 1451 34 (FROM RESONANCE PARAMETERS) = 3936 6337 1451 35 6337 1451 36 COMPUTED RESONANCE INTEGRAL 6337 1451 37 (FROM RESONANCE PARAMETERS) = 23173 6337 1451 38 ABOVE 35 EV = 272 6337 1451 39 TOTAL = 23445 6337 1451 40 REFERENCES (RESONANCE PARAMETERS) 6337 1451 41 1. S. F. MUGHABGHAB, NEUTRON CROSS SECTIONS, VOL. 1, 6337 1451 42 PART B: Z=61-100, ACADEMIC PRESS, NEW YORK (1984) 6337 1451 43 6337 1451 44 *****************************************************************6337 1451 45 MF=2 MT=151 NO RESONANCE PARAMETERS GIVEN EXCEPT AP. 6337 1451 46 6337 1451 47 MF=3 MT= 1 TOTAL CROSS SECTION CALCULATED WITH A DEFORMED 6337 1451 48 POTENTIAL FROM REF. (4) FOR E .GT. EH. 6337 1451 49 6337 1451 50 MF=3 MT= 2 ELASTIC CROSS SECTION FROM SIGT-SIGCAP-SIGIN 6337 1451 51 E .GT. EH, FROM 4PI*AP**2 FOR E .LT. EH. 6337 1451 52 6337 1451 53 MF=3 MT= 4,51,52,.,.,91 INELASTIC CROSS SECTIONS CALCULATED 6337 1451 54 USING COMNUC-3 REFS.(5,6). LEVEL SCHEME6337 1451 55 DATA FROM NUCLEAR DATA TABLES AND 6337 1451 56 S IGARASI(JAPAN) PRIVATE COMMUNICATION.6337 1451 57 6337 1451 58 MF=3 MT= 16(N,2N),17(N,3N),22(N,ND),28(N,NP),103(N,P),104(N,D), 6337 1451 59 105(N,T),106(N,HE3),107(N,HE4) CALCULATED USING 6337 1451 60 THRESH CODE REF(7). 6337 1451 61 6337 1451 62 MF=3 MT=102 NEUTRON CAPTURE EVALUATED USING COMNUC-3 AND NCAP 6337 1451 63 IN REFS.(1,2) FOR E .GT. EH. A 1/V COMPONENT WAS ADDED TO6337 1451 64 GIVE THE 2200 M/S CROSS SECTION OF REF.(3) FOR E .LT. EH 6337 1451 65 A 1/V COMPONENT WAS ADDED TO GIVE THE 2200M/S 6337 1451 66 CROSS SECTION OF REF.(3) FOR E