IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.70590E+4 5.84300E+1 0 0 1 12735 1451 1 0.0 0.0 0 0 0 02735 1451 2 0.0 0.0 0 0 167 62735 1451 3 27-Co- 59 1USALRL EVAL- 76 2735 1451 4 2735 1451 5 IDENTIFIER=ENDL 2735 2735 1451 6 FORMAT= ENDF/B-5 2735 1451 7 =============================================================== 2735 1451 8 ======================== For MF = 26 ======================== 2735 1451 9 2735 1451 10 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 2735 1451 11 2735 1451 12 TEXT= 2735 1451 13 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2735 1451 14 LIBRARY 2735 1451 15 =============================================================== 2735 1451 16 ======================== For MF = 16 ======================== 2735 1451 17 2735 1451 18 2.70590+ 4 5.84269+ 1 1 0 0 12735 1451 19 0.0 + 0 0.0 + 0 0 0 0 02735 1451 20 0.0 + 0 0.0 + 0 0 0 90 32735 1451 21 27-Co- 59 BNL EVAL-JUN77 S.MUGHABGHAB 2735 1451 22 DIST-AUG79 790328 2735 1451 23 P.C.TO THE NORMALIZATION AND STANDARDS SUBCOMMITTEE FEB 79 2735 1451 24 THE PRESENT EVALUATION OF CO-59 FOR ENDF/B V IS BASED ON THAT 2735 1451 25 OF ENDF/BIV,UPDATING THE FILES WHERE NEW EXPERIMENTAL DATA IS 2735 1451 26 AVAILABLE 2735 1451 27 FILE=2 RESONANCE PARAMETERS 2735 1451 28 **************************** 2735 1451 29 THE RESONANCE PARAMETERS FROM 132 EV TO 84.4 KEV ARE ADOPTED 2735 1451 30 FROM THE EVALUATION OF REF.1 WITH MINOR CHANGES. WEAK 2735 1451 31 RESONANCES OBSERVED IN CAPTURE DATA OF REF 2-3 ARE INCLUDED AS 2735 1451 32 P-WAVE RESONANCES. SPINS OF THE WEAK RESONANCES ARE ASSIGNED 2735 1451 33 RANDOMLY IN ORDER TO OBEY (2J+1) LAW. FROM G.GN.GG/GT VALUES, 2735 1451 34 GN VALUES ARE DERIVED BY ASSUMING A RADIATIVE WIDTH OF 0.22 EV.2735 1451 35 WHEN THE G.GN.GG/GT VALUES APPROACHE A VALUE OF G.GG, A 2735 1451 36 SCATTERING WIDTH OF 2.0 EV IS ASSUMED, AND THEN A RADIATIVE 2735 1451 37 WIDTH IS DERIVED FOR AN ASSIGNED SPIN VALUE. 2735 1451 38 THE PARAMETERS OF A BOUND LEVEL ARE DERIVED IN ORDER TO SATISFY2735 1451 39 THE RECENT POLARIZATION DATA OF ABRAGAM ET AL(REF.4) AND 2735 1451 40 THERMAL SCATTERING DATA OF REF.5 AND THERMAL TOTAL DATA OF 2735 1451 41 REF.6 2735 1451 42 THE RESONANCE REGION WAS TERMINATED AT ABOUT 85 KEV BECAUSE OF 2735 1451 43 THE IMPORTANT CONTRIBUTION OF P-WAVE RESONANCES TO THE CAPTURE 2735 1451 44 CROSS SECTION AS MEASURED IN REF.1-2. THE PREVIOUS EVALUATION 2735 1451 45 WAS BASED SOLELY ON TOTAL CROSS SECTION DATA OF REF.7. 2735 1451 46 IN THE PRESENT EVALUATION,THE FOLLOWING THERMAL CROSS SECTIONS 2735 1451 47 AND CAPTURE RESONANCE INTEGRAL RESULT 2735 1451 48 CAPTURE C/S= 37.233 B 2735 1451 49 SCATTERING C/S= 5.364 B 2735 1451 50 TOTAL C/S= 42.597 B 2735 1451 51 CAPTURE INTEGRAL = 73.78 B 2735 1451 52 FILE=3 NEUTRON CROSS SECTIONS 2735 1451 53 ****************************** 2735 1451 54 MT=16 (N,2N) REACTION CROSS SECTION 2735 1451 55 ------------------------------------------ 2735 1451 56 CONSIDERABLE EXPERIMENTAL DATA IS AVAILABLE FOR THIS REACTION. 2735 1451 57 FOR A BRIEF SUMMARY OF OLDER DATA SETS, SEE BNL-325(1966) 2735 1451 58 REF.8. IN THIS EVALUATION,EMPHASIS IS PLACED ON THE MORE RECENT2735 1451 59 DATA SETS (REF. 9-10) GUIDED BY NUCLEAR MODEL CALCULATIONS 2735 1451 60 WHICH ARE BASED ON UHL S CODE.(REF11) 2735 1451 61 MT=102,CAPTURE CROSS SECTION 2735 1451 62 -------------------------------- 2735 1451 63 IN THE ENERGY REGION 85-1000 KEV, THE CAPTURE CROSS SECTION IS 2735 1451 64 BASED ON DATA OF SPENCER AND MACKLIN (REF.2).DATA OF POENITZ 2735 1451 65 (REF.13) WAS NOT YET RELEASED. BETWEEN 1.0 TO 6.2 MEV, IT IS 2735 1451 66 BASED ON DATA OF REFS.14-15. BETWEEN 6.2-20 MEV, THE EVALUATION2735 1451 67 IS BASED ON MODEL CALCULATIONS(REF.12), GUIDED BY SYSTEMATICS 2735 1451 68 FROM NEIGHBORING ODD NUCLEUS MN-55(REF.16). THE 14.7 MEV 2735 1451 69 VALUE IS NORMALISED TO A WEIGHTED AVERAGE VALUE OF 0.830 MB. 2735 1451 70 (REFS.17,18) 2735 1451 71 MT=107, (N,A) REACTION CROSS SECTION 2735 1451 72 ------------------------------------------ 2735 1451 73 ALTHOUGH TWO NEW DATA SETS (REF.19-20) ARE AVAILABLE,IT WAS 2735 1451 74 FELT THAT THESE WOULD NOT APPRECIABLY ALTER THE PREVIOUS 2735 1451 75 ENDF/B IV EVALUATION WHICH IS BASED ON J.D.JENKINS 2735 1451 76 EVALUATION (AP.1972) P.C. TO NORM. AND STAND SUB. 8/72 2735 1451 77 LIST OF REFERENCES 2735 1451 78 1. S.F.MUGHABGHAB AND T.J.KRIEGER,BNL-NCS-50468(ENDF-229),1975 2735 1451 79 2. R.R.SPENCER AND R.L.MACKIIN,NUCL.SCIENCE,ENG.,61,346(1976) 2735 1451 80 3. R.R.SPENCER AND H.BEER,NUCL.SCIENCE,ENG.,60,390(1976) 2735 1451 81 4. A.ABRAGAM ET.AL. JOURNAL DE PHYSIQUE-LETTERS,36,L263(1975) 2735 1451 82 AND PRIVATE COMMUNICATION 2735 1451 83 5. L.KOESTER ET.AL. Z. PHYSIK,271,201(1974) 2735 1451 84 6. W.DILG,ET.AL.,Z.PHYSIK,264,427(1973) 2735 1451 85 7. J.B.GARG,J.RAINWATER,AND W.W.HAVENS,BAP,8,334,(1963) AND 2735 1451 86 8. M.D.GOLDBERG,S.F.MUGHABGHAB,B.A.MAGURNO,AND V.M.MAY,BNL-325, 2735 1451 87 SECOND ED., SUPP.2,(1966) 2735 1451 88 9.J. FREHAUT AND G.MOSINKI,CEAR-4627 (1974) 2735 1451 89 10.L.R.VEESER AND E.D.ARTHUR PROCEEDINGS OF INTERNATIONAL 2735 1451 90 CONF.ON INTERACTIONS OF NEUTRONS WITH NUCLEI,1351(1976) 2735 1451 91 (LOWELL) AND PRIVATE COMMUNICATION. 2735 1451 92 11.M. UHL, NUCL.PHYS.,A184,253(1972) 2735 1451 93 12.C. DUNFORD,AI-AEC-12931(1970) 2735 1451 94 13.W.P.POENITZ,NUCLEAR CROSS SECTIONS AND TECHNOLOGY,VOL.2,901, 2735 1451 95 (1975) WASHINGTON,D.C. 2735 1451 96 14.A.E.JOHNSRUD,M.G.SILBERT,AND H.H.BARCHALL, PHYS.REV.,116,927 2735 1451 97 (1959) 2735 1451 98 15.A.PAULSEN,ZEIT. PHYSIK,205,226(1967) 2735 1451 99 16.H.O.MENLOVE,K.L.COOP,AND H.A.GRENCH, PHYS.REV,163,1299(1967) 2735 1451 100 17.F.RIGAUD,J.L.IRIGARAY,AND G.Y.PETIT,NUCL.PHYS.,A173,551, 2735 1451 101 (1971) 2735 1451 102 18.F. CVELBAR ET.AL.NUCL.PHYS.,A130,401(1969) 2735 1451 103 19.J.C.ROBERTSON,B.AUDRIC,AND P.KOLOWSKI,JOUR.NUCL.ENERGY,27, 2735 1451 104 (1973) 2735 1451 105 20.K.RUSEK ET.AL.,INDC(POL)- 6/G,PAGE10(1976) 2735 1451 106 2735 1451 107 ***************** PROGRAM LINEAR (VERSION 82-1) *****************2735 1451 108 DATA LINEARIZED USING A MAXIMUM ERROR OF 0.100 PER-CENT 2735 1451 109 ***************** PROGRAM RECENT (VERSION 81-2) *****************2735 1451 110 DATA RECONSTRUCTED USING A MAXIMUM ERROR OF 0.100 PER-CENT 2735 1451 111 =============================================================== 2735 1451 112 ==================== For MF = 103 and 107 =================== 2735 1451 113 2735 1451 114 2.70590+ 4 5.84183+ 1 0 0 1 12735 1451 115 0.0 + 0 0.0 + 0 0 0 0 02735 1451 116 0.0 + 0 0.0 + 0 0 0 34 32735 1451 117 27-Co- 59 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2735 1451 118 YK-3,(42),60 ,8109 DIST-JAN81 820212 2735 1451 119 IDENTIFIER=INDL 2730 REV1 2735 1451 120 FORMAT= ENDF/B-5 2735 1451 121 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2735 1451 122 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2735 1451 123 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2735 1451 124 TEXT= 2735 1451 125 27-CO-59(N,2N)27-CO-58 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 2735 1451 126 27-CO-59(N,P)26-FE-59 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2735 1451 127 27-CO-59(N,A)25-MN-56 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2735 1451 128 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2735 1451 129 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2735 1451 130 OBNINSK,USSR). 2735 1451 131 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2735 1451 132 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2735 1451 133 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2735 1451 134 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2735 1451 135 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2735 1451 136 KONSTANTY,32(1),PAGE 105,1979 2735 1451 137 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2735 1451 138 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2735 1451 139 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2735 1451 140 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2735 1451 141 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2735 1451 142 YAD. KOSTANTY 3,(42),P.60,(1981) 2735 1451 143 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2735 1451 144 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2735 1451 145 REACTION | V.2,P.271,IAEA,VIENNA) 2735 1451 146 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2735 1451 147 -------------|-------------|---------------|------------------ 2735 1451 148 27-CO-59(N,2N) | 0.174 | 0.145 | 0.229 2735 1451 149 27-CO-59(N,P) | 1.14 | 1.08 | 1.10 2735 1451 150 27-CO-59(N,A) | 0.147 | 0.135 | 0.151 2735 1451 151 =============================================================== 2735 1451 152 ***************** Program LINEAR (VERSION 2002-1) ***************2735 1451 153 For All Data Greater than 1.0000E-10 barns in Absolute Value 2735 1451 154 Data Linearized to Within an Accuracy of .100000000 per-cent 2735 1451 155 ***************** Program FIXUP (Version 2002-1) ****************2735 1451 156 Corrected ZA/AWR in All Sections-----------------------------Yes 2735 1451 157 Corrected Thresholds-----------------------------------------Yes 2735 1451 158 Extended Cross Sections to 20 MeV----------------------------No 2735 1451 159 Allow Cross Section Deletion---------------------------------No 2735 1451 160 Allow Cross Section Reconstruction---------------------------No 2735 1451 161 Make All Cross Sections Non-Negative-------------------------Yes 2735 1451 162 Delete Energies Not in Ascending Order-----------------------Yes 2735 1451 163 Deleted Duplicate Points-------------------------------------Yes 2735 1451 164 Check for Ascending MAT/MF/MT Order--------------------------Yes 2735 1451 165 Check for Legal MF/MT Numbers--------------------------------Yes 2735 1451 166 Allow Creation of Missing Sections---------------------------No 2735 1451 167 Allow Insertion of Energy Points-----------------------------No 2735 1451 168 Create Uniform Energy Grid-----------------------------------No 2735 1451 169 Delete Section if Cross Section =0 at All Energies-----------Yes 2735 1451 170 1 451 176 12735 1451 171 3 16 8 12735 1451 172 3 26 8 12735 1451 173 3 103 19 12735 1451 174 3 107 28 12735 1451 175 33 16 8 12735 1451 176 2735 1 0 177 2735 0 0 178 2.70590E+4 5.84300E+1 0 99 0 02735 3 16 179 0.0 -1.04610E+7 0 0 1 152735 3 16 180 15 2 2735 3 16 181 10640000.0 0.0 11000000.0 .020000000 11500000.0 .1500000002735 3 16 182 12500000.0 .400000000 13000000.0 .535000000 13500000.0 .6500000002735 3 16 183 14000000.0 .750000000 14500000.0 .795000000 15000000.0 .8250000002735 3 16 184 16000000.0 .855000000 17000000.0 .865000000 17500000.0 .8650000002735 3 16 185 18500000.0 .855000000 19500000.0 .825000000 20000000.0 .8000000002735 3 16 186 2735 3 0 187 2.70590E+4 5.84300E+1 0 1 0 02735 3 26 188 2.93000E+2-1.04800E+7 0 0 1 132735 3 26 189 13 2 2735 3 26 190 10660000.0 0.0 11000000.0 .014000000 12000000.0 .1960000002735 3 26 191 12500000.0 .280000000 13000000.0 .350000000 13500000.0 .4060000002735 3 26 192 14000000.0 .448000000 15000000.0 .497000000 16000000.0 .5250000002735 3 26 193 17000000.0 .546000000 18000000.0 .560000000 19000000.0 .5670000002735 3 26 194 20000000.0 .560000000 2735 3 26 195 2735 3 0 196 2.70590E+4 5.84300E+1 0 0 0 02735 3103 197 2.93000E+2-7.87000E+5 0 0 1 472735 3103 198 47 2 2735 3103 199 800469.108 0.0 3400000.00 0.0 3500000.00 .0010000002735 3103 200 3600000.00 .001300000 3700000.00 .001700000 3800000.00 .0020000002735 3103 201 4000000.00 .003000000 4100000.00 .003355000 4200000.00 .0037200002735 3103 202 4300000.00 .004095000 4400000.00 .004480000 4500000.00 .0048750002735 3103 203 4700000.00 .005695000 4900000.00 .006555000 5100000.00 .0074550002735 3103 204 5300000.00 .008395000 5500000.00 .009375000 5700000.00 .0103900002735 3103 205 5900000.00 .011450000 6100000.00 .012550000 6400000.00 .0142800002735 3103 206 6700000.00 .016090000 7000000.00 .018000000 8000000.00 .0250000002735 3103 207 8400000.00 .027680000 8800000.00 .030520000 9000000.00 .0320000002735 3103 208 10100000.0 .040840000 10600000.0 .044920000 11300000.0 .0503100002735 3103 209 11700000.0 .053110000 12300000.0 .056920000 12600000.0 .0584800002735 3103 210 12900000.0 .059680000 13200000.0 .060520000 13500000.0 .0610000002735 3103 211 13800000.0 .061120000 14000000.0 .061000000 14500000.0 .0597500002735 3103 212 14900000.0 .058390000 15100000.0 .057500000 17100000.0 .0475400002735 3103 213 17600000.0 .045120000 18000000.0 .043000000 18500000.0 .0398700002735 3103 214 19000000.0 .037000000 20000000.0 .032000000 2735 3103 215 2735 3 0 216 2.70590E+4 5.84300E+1 0 0 0 02735 3107 217 2.93000E+2 3.15000E+6 0 0 1 742735 3107 218 74 2 2735 3107 219 .001000000 0.0 .025300000 0.0 5000000.00 0.0 2735 3107 220 5100000.00 5.60000E-5 5200000.00 .000124000 5300000.00 .0002040002735 3107 221 5400000.00 .000296000 5500000.00 .000400000 5600000.00 .0005160002735 3107 222 5700000.00 .000644000 5800000.00 .000784000 5900000.00 .0009360002735 3107 223 6000000.00 .001100000 6100000.00 .001253000 6200000.00 .0014240002735 3107 224 6300000.00 .001611000 6400000.00 .001816000 6500000.00 .0020370002735 3107 225 6600000.00 .002276000 6700000.00 .002531000 6800000.00 .0028040002735 3107 226 6900000.00 .003093000 7000000.00 .003400000 7100000.00 .0037680002735 3107 227 7300000.00 .004526000 7500000.00 .005312000 7700000.00 .0061260002735 3107 228 7900000.00 .006968000 8000000.00 .007400000 8400000.00 .0093160002735 3107 229 8700000.00 .010720000 9000000.00 .012100000 9200000.00 .0130800002735 3107 230 9400000.00 .014020000 9500000.00 .014460000 9600000.00 .0148000002735 3107 231 9700000.00 .015400000 9800000.00 .015900000 9900000.00 .0161200002735 3107 232 10000000.0 .016500000 10300000.0 .017290000 10600000.0 .0182000002735 3107 233 10900000.0 .019230000 11000000.0 .019600000 11500000.0 .0219000002735 3107 234 12300000.0 .025280000 12600000.0 .026390000 12900000.0 .0273300002735 3107 235 13200000.0 .028180000 13400000.0 .028640000 13600000.0 .0289800002735 3107 236 13800000.0 .029200000 14000000.0 .029300000 14300000.0 .0291100002735 3107 237 14600000.0 .028750000 14900000.0 .028220000 15000000.0 .0280000002735 3107 238 15600000.0 .026150000 16000000.0 .024800000 16700000.0 .0221700002735 3107 239 17000000.0 .021000000 17800000.0 .017700000 18000000.0 .0169000002735 3107 240 18200000.0 .015930000 18400000.0 .015050000 18600000.0 .0142700002735 3107 241 18800000.0 .013590000 18900000.0 .013280000 19000000.0 .0130000002735 3107 242 19200000.0 .012620000 19400000.0 .012280000 19600000.0 .0119800002735 3107 243 19800000.0 .011720000 20000000.0 .011500000 2735 3107 244 2735 3 0 245 2735 0 0 246 2.70590E+4 5.84300E+1 0 0 0 1273533 16 247 0.00000+ 0 0.00000+ 0 0 16 0 2273533 16 248 0.00000+ 0 0.00000+ 0 0 1 6 3273533 16 249 1.00000- 5 0.00000+ 0 1.06400+ 7 2.50000- 3 2.00000+ 7 0.00000+ 0273533 16 250 0.00000+ 0 0.00000+ 0 0 1 16 8273533 16 251 1.00000- 5 0.00000+ 0 1.06400+ 7 1.22500- 1 1.20000+ 7 4.00000- 2273533 16 252 1.30000+ 7 4.90000- 3 1.40000+ 7 9.00000- 4 1.50000+ 7 2.50000- 3273533 16 253 1.90000+ 7 2.50000- 3 2.00000+ 7 0.00000+ 0 273533 16 254 273533 0 255 2735 0 0 256 0 0 0 257 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0