IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.20480E+4 4.75400E+1 0 0 1 12235 1451 1 0.0 0.0 0 0 0 02235 1451 2 0.0 0.0 0 0 105 52235 1451 3 22-Ti- 48 1USALRL EVAL- 76 2235 1451 4 2235 1451 5 IDENTIFIER=ENDL 2235 2235 1451 6 FORMAT= ENDF/B-5 2235 1451 7 =============================================================== 2235 1451 8 ======================= For MF = 107 ======================== 2235 1451 9 2235 1451 10 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 2235 1451 11 2235 1451 12 TEXT= 2235 1451 13 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2235 1451 14 LIBRARY 2235 1451 15 =============================================================== 2235 1451 16 ======================= For MF = 28 ======================== 2235 1451 17 2.20480+ 4 4.75360+ 1 0 0 0 22235 1451 18 0.0 + 0 0.0 + 0 0 0 0 02235 1451 19 0.0 + 0 0.0 + 0 0 0 33 32235 1451 20 22-Ti- 48 ANL EVAL-JAN77 C.PHILIS,O.BERSILLON,D.SMITH ETC.2235 1451 21 DIST-AUG79 810728 2235 1451 22 ** 2235 1451 23 DOCUMENTATION ANL/NDM-27 (N,P) ANL/NDM-28 (N,NP) 2235 1451 24 ** 2235 1451 25 (N,P) EVAL IN ENERGY RANGES 4.70E+06 TO 1.0E+07 AND 2235 1451 26 1.25E+07 TO 2.0E+07 BASED ON EXPERIMENTAL DATA. INTERPOLATION 2235 1451 27 AND EXTRAPOLATION TO OTHER ENERGIES BASED ON THEORETICAL CALCS 2235 1451 28 PERFORMED AT BRUYERES LE CHATEL USING CODE DEVELOPED BY J.JARRE 2235 1451 29 ** 2235 1451 30 (N,NP) AND (N,D) CROSS SECTIONS EVAL BY C.Y.FU ORNL 2235 1451 31 (N,D) CROSS SECTIONS WERE BASED ON THE MEASUREMENT OF HAIGHT 2235 1451 32 AND GRIMES(UCRL-80235) AT 14.8 MEV. THE SHAPE OF THE CROSS- 2235 1451 33 SECTION CURVE WAS ASSUMED TO BE THAT OF (N,NP).(N,D) AND (N,NP) 2235 1451 34 ADDED TOGETHER FOR DOSIMETRY PURPOSES. 2235 1451 35 REFERENCES 2235 1451 36 AL61 ALLAN D. NP24,274,61 2235 1451 37 BO65 BORMANN M.ET.AL.EANDC(E)57,17,65 2235 1451 38 CR62 CROSS W.AND PAI H. EANDC(CAN)-16 1962 2235 1451 39 FU79 C.Y.FU PRIVATE COMM 1979 2235 1451 40 GA62 GABBARD F.AND KERN B. PR128,1276,62 2235 1451 41 GH71 GHORAI S.ET.AL.JNE25,319,71 2235 1451 42 HI62 HILLMAN M. NP37,78,62 2235 1451 43 LE69 LEVKOVSKII YF10,44,69 2235 1451 44 LU71 LUKIC Y.AND CARROLL E. NSE43,233,71 2235 1451 45 MA75 MANNHART W.AND VONACH H. ZP,A272,279,75 2235 1451 46 PA66 PAI H. CJP44,2337,66 2235 1451 47 PO59 POULARIKAS A.AND FINK R. PR115,989,59 2235 1451 48 SM75 SMITH D.L.AND MEADOWS J. ANL/NDM-10,75 2235 1451 49 TI68 TIKKU L.ET.AL. SYMP.ON NUC CROSS SEC TECH WASH.1968 2235 1451 50 VO68 VONACH H.ET.AL. SYMP ON NUC CROSS SEC TECH WASH.1968 2235 1451 51 ***************** PROGRAM LINEAR (VERSION 82-1) *****************2235 1451 52 DATA LINEARIZED USING A MAXIMUM ERROR OF 0.100 PER-CENT 2235 1451 53 =============================================================== 2235 1451 54 ======================= For MF = 103 ======================== 2235 1451 55 2.20480+ 4 4.75361+ 1 0 0 1 12235 1451 56 0.0 + 0 0.0 + 0 0 0 0 02235 1451 57 0.0 + 0 0.0 + 0 0 0 30 22235 1451 58 22-Ti- 48 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2235 1451 59 YK-3,(42),60 ,8109 DIST-JAN81 820212 2235 1451 60 IDENTIFIER=INDL 2250 REV1 2235 1451 61 FORMAT= ENDF/B-5 2235 1451 62 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2235 1451 63 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2235 1451 64 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2235 1451 65 TEXT= 2235 1451 66 22-TI-48(N,P)21-SC-48 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2235 1451 67 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2235 1451 68 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2235 1451 69 OBNINSK,USSR). 2235 1451 70 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2235 1451 71 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2235 1451 72 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2235 1451 73 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2235 1451 74 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2235 1451 75 KONSTANTY,32(1),PAGE 105,1979 2235 1451 76 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2235 1451 77 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2235 1451 78 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2235 1451 79 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2235 1451 80 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2235 1451 81 YAD. KOSTANTY 3,(42),P.60,(1981) 2235 1451 82 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2235 1451 83 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2235 1451 84 REACTION | V.2,P.271,IAEA,VIENNA) 2235 1451 85 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2235 1451 86 -------------|-------------|---------------|------------------ 2235 1451 87 22-TI-48(N,P) | 0.262 | 0.241 | 0.269 2235 1451 88 2235 1451 89 =============================================================== 2235 1451 90 ***************** Program LINEAR (VERSION 2002-1) ***************2235 1451 91 For All Data Greater than 1.0000E-10 barns in Absolute Value 2235 1451 92 Data Linearized to Within an Accuracy of .100000000 per-cent 2235 1451 93 ***************** Program FIXUP (Version 2002-1) ****************2235 1451 94 Corrected ZA/AWR in All Sections-----------------------------Yes 2235 1451 95 Corrected Thresholds-----------------------------------------Yes 2235 1451 96 Extended Cross Sections to 20 MeV----------------------------No 2235 1451 97 Allow Cross Section Deletion---------------------------------No 2235 1451 98 Allow Cross Section Reconstruction---------------------------No 2235 1451 99 Make All Cross Sections Non-Negative-------------------------Yes 2235 1451 100 Delete Energies Not in Ascending Order-----------------------Yes 2235 1451 101 Deleted Duplicate Points-------------------------------------Yes 2235 1451 102 Check for Ascending MAT/MF/MT Order--------------------------Yes 2235 1451 103 Check for Legal MF/MT Numbers--------------------------------Yes 2235 1451 104 Allow Creation of Missing Sections---------------------------No 2235 1451 105 Allow Insertion of Energy Points-----------------------------No 2235 1451 106 Create Uniform Energy Grid-----------------------------------No 2235 1451 107 Delete Section if Cross Section =0 at All Energies-----------Yes 2235 1451 108 1 451 113 12235 1451 109 3 28 17 12235 1451 110 3 103 22 12235 1451 111 3 107 10 12235 1451 112 33 28 4 12235 1451 113 2235 1 0 114 2235 0 0 115 2.20480E+4 4.75400E+1 0 0 0 02235 3 28 116 0.0 -1.14460E+7 0 0 1 412235 3 28 117 41 2 2235 3 28 118 11686000.0 0.0 13000000.0 .003000000 13125000.0 .0032237102235 3 28 119 13218744.0 .003402370 13359368.0 .003689100 13500000.0 .0040000002235 3 28 120 13600000.0 .004400000 13700000.0 .004754750 13775000.0 .0050394502235 3 28 121 13887496.0 .005498790 14000000.0 .006000000 14075000.0 .0064192902235 3 28 122 14169328.0 .006988530 14248280.0 .007503580 14336208.0 .0081219602235 3 28 123 14402152.0 .008618960 14501072.0 .009422070 14600000.0 .0103000002235 3 28 124 14717184.0 .011248600 14812888.0 .012087800 14915424.0 .0130565002235 3 28 125 15007712.0 .013994600 15100000.0 .015000000 15261712.0 .0164183002235 3 28 126 15397056.0 .017707900 15547792.0 .019263600 15703232.0 .0210113002235 3 28 127 15809216.0 .022292900 15936400.0 .023934400 16000000.0 .0248000002235 3 28 128 16206248.0 .027071000 16346872.0 .028737500 16515624.0 .0308733002235 3 28 129 16600000.0 .032000000 16850000.0 .034691100 17107792.0 .0377035002235 3 28 130 17389056.0 .041288900 17700000.0 .045515200 18000000.0 .0497000002235 3 28 131 18600000.0 .049000000 20000000.0 .046900000 2235 3 28 132 2235 3 0 133 2.20480E+4 4.75400E+1 0 0 0 02235 3103 134 2.93000E+2-3.20000E+6 0 0 1 572235 3103 135 57 2 2235 3103 136 3267311.74 0.0 5000000.00 0.0 5100000.00 6.50000E-52235 3103 137 5200000.00 .000160000 5300000.00 .000285000 5400000.00 .0004400002235 3103 138 5500000.00 .000625000 5600000.00 .000840000 5700000.00 .0010850002235 3103 139 5800000.00 .001360000 5900000.00 .001665000 6000000.00 .0020000002235 3103 140 7000000.00 .007000000 7100000.00 .007410000 7200000.00 .0078400002235 3103 141 7300000.00 .008290000 7400000.00 .008760000 7500000.00 .0092500002235 3103 142 7600000.00 .009760000 7800000.00 .010840000 8000000.00 .0120000002235 3103 143 8200000.00 .013320000 8400000.00 .014680000 8700000.00 .0167900002235 3103 144 9000000.00 .019000000 9300000.00 .021290000 9700000.00 .0244900002235 3103 145 10300000.0 .029490000 10600000.0 .032160000 10900000.0 .0350100002235 3103 146 11100000.0 .037050000 11600000.0 .042480000 12000000.0 .0470000002235 3103 147 12200000.0 .049880000 12400000.0 .052520000 12600000.0 .0549200002235 3103 148 12800000.0 .057080000 13000000.0 .059000000 13200000.0 .0606800002235 3103 149 13500000.0 .062750000 13800000.0 .064280000 14100000.0 .0652700002235 3103 150 14400000.0 .065720000 14500000.0 .065750000 14800000.0 .0654800002235 3103 151 15000000.0 .065000000 15600000.0 .061520000 16000000.0 .0590000002235 3103 152 16400000.0 .055960000 16800000.0 .053240000 17000000.0 .0520000002235 3103 153 18000000.0 .047000000 18300000.0 .045180000 18600000.0 .0436400002235 3103 154 18900000.0 .042360000 19000000.0 .042000000 20000000.0 .0400000002235 3103 155 2235 3 0 156 2.20480E+4 4.75400E+1 0 0 0 02235 3107 157 2.93000E+2-2.03100E+6 0 0 1 192235 3107 158 19 2 2235 3107 159 2073721.92 0.0 6967000.00 0.0 7267000.00 .0004475002235 3107 160 7567000.00 .001760000 7867000.00 .003852000 8167000.00 .0065890002235 3107 161 8467000.00 .009806000 9367000.00 .020530000 9967000.00 .0270100002235 3107 162 10570000.0 .032080000 10870000.0 .034020000 11470000.0 .0368200002235 3107 163 12370000.0 .038950000 13270000.0 .039720000 17470000.0 .0400000002235 3107 164 18070000.0 .039500000 18670000.0 .037310000 19870000.0 .0296100002235 3107 165 20000000.0 .029610000 2235 3107 166 2235 3 0 167 2235 0 0 168 2.20480E+4 4.75400E+1 0 0 0 1223533 28 169 0.00000+ 0 0.00000+ 0 0 28 0 1223533 28 170 0.00000+ 0 0.00000+ 0 0 1 6 3223533 28 171 1.00000- 5 0.00000+ 0 1.16860+ 7 9.00000- 2 2.00000+ 7 0.00000+ 0223533 28 172 223533 0 173 2235 0 0 174 0 0 0 175 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0