IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.50550E+4 5.49381E+1 0 0 1 12530 1451 1 0.0 0.0 0 0 0 02530 1451 2 0.0 0.0 0 0 70 42530 1451 3 25-Mn- 55 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2530 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 2530 1451 5 IDENTIFIER=INDL 2530 REV1 2530 1451 6 FORMAT= ENDF/B-5 2530 1451 7 =============================================================== 2530 1451 8 ======================== For MF = 16 ======================== 2530 1451 9 2530 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2530 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2530 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2530 1451 13 TEXT= 2530 1451 14 25-MN-55(N,2N)25-MN-54 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 2530 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2530 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2530 1451 17 OBNINSK,USSR). 2530 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2530 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2530 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2530 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2530 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2530 1451 23 KONSTANTY,32(1),PAGE 105,1979 2530 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2530 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2530 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2530 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2530 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2530 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 2530 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2530 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2530 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 2530 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2530 1451 34 -------------|-------------|---------------|------------------ 2530 1451 35 25-MN-55(N,2N)| 0.231 | 0.193 | 0.300 2530 1451 36 =============================================================== 2530 1451 37 =================== For MF = 103 and 107 ==================== 2530 1451 38 2530 1451 39 0.25055E 05 0.5447E 02 0 0 1 12530 1451 40 0.0 0.0 0 0 0 02530 1451 41 0.0 0.0 0 0 12 32530 1451 42 25-Mn- 55 1USALRL EVAL- 77 2530 1451 43 2530 1451 44 IDENTIFIER=ENDL 2535 2530 1451 45 FORMAT= ENDF/B-5 2530 1451 46 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 2530 1451 47 840502 DATA WERE RENORMALIZED BY VP, (K=1.29) 2530 1451 48 TEXT= For MT=103 2530 1451 49 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2530 1451 50 LIBRARY 2530 1451 51 TEXT= For MT=107 2530 1451 52 25-Mn- 55 4CCPFEI EVAL- 80 2530 1451 53 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM BOSPOR LIBRARY 2530 1451 54 =============================================================== 2530 1451 55 ***************** Program LINEAR (VERSION 2002-1) ***************2530 1451 56 For All Data Greater than 1.0000E-10 barns in Absolute Value 2530 1451 57 Data Linearized to Within an Accuracy of .100000000 per-cent 2530 1451 58 ***************** Program FIXUP (Version 2002-1) ****************2530 1451 59 Corrected ZA/AWR in All Sections-----------------------------Yes 2530 1451 60 Corrected Thresholds-----------------------------------------Yes 2530 1451 61 Extended Cross Sections to 20 MeV----------------------------No 2530 1451 62 Allow Cross Section Deletion---------------------------------No 2530 1451 63 Allow Cross Section Reconstruction---------------------------No 2530 1451 64 Make All Cross Sections Non-Negative-------------------------Yes 2530 1451 65 Delete Energies Not in Ascending Order-----------------------Yes 2530 1451 66 Deleted Duplicate Points-------------------------------------Yes 2530 1451 67 Check for Ascending MAT/MF/MT Order--------------------------Yes 2530 1451 68 Check for Legal MF/MT Numbers--------------------------------Yes 2530 1451 69 Allow Creation of Missing Sections---------------------------No 2530 1451 70 Allow Insertion of Energy Points-----------------------------No 2530 1451 71 Create Uniform Energy Grid-----------------------------------No 2530 1451 72 Delete Section if Cross Section =0 at All Energies-----------Yes 2530 1451 73 1 451 77 12530 1451 74 3 16 17 12530 1451 75 3 103 10 12530 1451 76 3 107 8 12530 1451 77 2530 1 0 78 2530 0 0 79 2.50550E+4 5.49381E+1 0 0 0 02530 3 16 80 2.93000E+2-1.02200E+7 0 0 1 402530 3 16 81 40 2 2530 3 16 82 10406027.5 0.0 10700000.0 0.0 10800000.0 .0250000002530 3 16 83 10900000.0 .060000000 11000000.0 .087000000 11100000.0 .1226000002530 3 16 84 11200000.0 .157300000 11300000.0 .191100000 11400000.0 .2241000002530 3 16 85 11500000.0 .256100000 11600000.0 .287300000 11700000.0 .3175000002530 3 16 86 11800000.0 .346900000 11900000.0 .375400000 12000000.0 .4030000002530 3 16 87 12200000.0 .455400000 12400000.0 .504200000 12600000.0 .5496000002530 3 16 88 12800000.0 .591600000 13000000.0 .630000000 13200000.0 .6636000002530 3 16 89 13500000.0 .708800000 13800000.0 .747600000 14000000.0 .7700000002530 3 16 90 14400000.0 .801400000 14800000.0 .828200000 15100000.0 .8451000002530 3 16 91 15600000.0 .867700000 16000000.0 .882000000 16700000.0 .8982000002530 3 16 92 17400000.0 .909300000 17800000.0 .910900000 18000000.0 .9100000002530 3 16 93 18100000.0 .910100000 18400000.0 .907300000 18700000.0 .9000000002530 3 16 94 19000000.0 .888000000 19400000.0 .863000000 19800000.0 .8324000002530 3 16 95 20000000.0 .815000000 2530 3 16 96 2530 3 0 97 2.50550E+4 5.49381E+1 0 0 0 02530 3103 98 2.93000E+2-1.82100E+6 0 0 1 212530 3103 99 21 2 2530 3103 100 1854146.40 0.0 5288000.00 0.0 5588000.00 .0010870002530 3103 101 5888000.00 .004242000 6188000.00 .009168000 6488000.00 .0154200002530 3103 102 7388000.00 .035920000 7688000.00 .043460000 8288000.00 .0539200002530 3103 103 8588000.00 .057700000 9188000.00 .062730000 9788000.00 .0652600002530 3103 104 11590000.0 .065910000 11890000.0 .066290000 12490000.0 .0628600002530 3103 105 14290000.0 .045360000 14890000.0 .040730000 15490000.0 .0374900002530 3103 106 16090000.0 .035500000 16990000.0 .034080000 20000000.0 .0334800002530 3103 107 2530 3 0 108 2.50550E+4 5.49381E+1 0 0 0 02530 3107 109 2.93000E+2-6.24000E+5 0 0 1 142530 3107 110 14 2 2530 3107 111 635358.238 0.0 8200000.00 0.0 8500000.00 .0013000002530 3107 112 9000000.00 .004000000 11000000.0 .016000000 12000000.0 .0210000002530 3107 113 13000000.0 .025000000 14000000.0 .028000000 15000000.0 .0290000002530 3107 114 16000000.0 .027000000 17000000.0 .023000000 18000000.0 .0170000002530 3107 115 19000000.0 .012000000 20000000.0 .006000000 2530 3107 116 2530 3 0 117 2530 0 0 118 0 0 0 119 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0