IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 4.91150+ 4 1.13920+ 2 1 0 34 14931 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 64931 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 34931 1451 3 0.00000+ 0 0.00000+ 0 0 0 235 84931 1451 4 49-In-115 ANL/CNDC EVAL-JAN90 S. CHIBA AND D.L. SMITH 4931 1451 5 REPORT ANL/NDM-115 DIST-FEB91 910201 4931 1451 6 ----IRDF-90 MAT#4931 4931 1451 7 -----INCIDENT NEUTRON DATA 4931 1451 8 ------ENDF-6 4931 1451 9 *****************************************************************4931 1451 10 REPORT ANL/NDM-115 DIST-DEC90 REV0-DEC90 901231 4931 1451 11 ENDF/B-VI MAT# REVISION 0 4931 1451 12 *****************************************************************4931 1451 13 CHINESE EVALUATION OF (N,2N) REACTION ADDED AT NDS 4931 1451 14 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451 15 4931 1451 16 IN-115(N,N')IN-115M DOSIMETRY REACTION 4931 1451 17 4931 1451 18 EVALUATED BY S.CHIBA AND D.L. SMITH, ANL, JANUARY 1990 4931 1451 19 4931 1451 20 PRODUCTION OF THE ISOMER IN-115M BY THE (N,N') PROCESS IS 4931 1451 21 ROUTINELY EMPLOYED FOR NEUTRON DOSIMETRY APPLICATIONS. THIS 4931 1451 22 ISOMER IS THE FIRST-EXCITED STATE OF THE ISOTOPE IN-115 (336 KEV 4931 1451 23 EXCITATION ENERGY). THE REACTION THRESHOLD ENERGY IS 339 KEV. 4931 1451 24 THE ISOTOPIC ABUNDANCE OF IN-115 IN NATURAL INDIUM IS 95.7 4931 1451 25 PERCENT. THE HALF LIFE OF IN-115M IS 4.486 HOURS. THE DECAY 4931 1451 26 MODES ARE - BETA MINUS (5 PERCENT) ISOMERIC TRANSITION (95.0 4931 1451 27 PERCENT). THE NUMBER OF DECAY 336-KEV GAMMA RAYS EMITTED PER 4931 1451 28 DISINTEGRATION OF IN-115M IS 0.459. 4931 1451 29 4931 1451 30 DOCUMENTATION FOR THIS EVALUATION IS PROVIDED BY A.B. SMITH ET 4931 1451 31 AL., REPORT ANL/NDM-115, ARGONNE NATIONAL LABORATORY (1990). 4931 1451 32 EVALUATED RESULTS FOR THIS REACTION ARE BASED ON EXPERIMENTAL 4931 1451 33 DATA. NUCLEAR MODEL CALCULATIONS WERE USED TO ESTIMATE THE CROSS 4931 1451 34 SECTION SHAPE NEAR THRESHOLD. THIS EVALUATION WAS CARRIED OUT 4931 1451 35 USING THE STATISTICAL LEAST-SQUARES METHOD. THE CODE GMA, AS 4931 1451 36 DEVELOPED BY W. POENITZ (1981) AND LATER REVISED BY M. SUGIMOTO 4931 1451 37 (1987) AND S. CHIBA (1990), WAS EMPLOYED FOR THIS ANALYSIS. 4931 1451 38 4931 1451 39 THE FOLLOWING FILE SECTIONS ARE INCLUDED - 4931 1451 40 MF= 1 GENERAL INFORMATION (MT=451) 4931 1451 41 MF= 8 RADIOACTIVITY DATA (MT=51) 4931 1451 42 MF=10 CROSS SECTION FOR RADIOACTIVE NUCLIDE 4931 1451 43 PRODUCTION (MT=51) 4931 1451 44 MF=40 DATA COVARIANCES FOR RADIOACTIVE NUCLIDE 4931 1451 45 PRODUCTION (MT=51) 4931 1451 46 49-IN-115 CNDC/CIAE EVAL-JUN91 CAI DUNJIU AND WANG ZISHENG 4931 1451 47 ---ENDF-6 FORMAT 4931 REVISION 0 4931 1451 48 4931 1451 49 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451 50 4931 1451 51 Evaluation of the 115-In(n,2n) 114m-In Reaction 4931 1451 52 Cross-section 4931 1451 53 Cai Dunjiu Yu Baosheng Wang Zisheng 4931 1451 54 Lu Hanlin Zhao Wenrong 4931 1451 55 Institute of Atomic Energy, China 4931 1451 56 The excitation function of 115-In(n, 2n) 114m-In reaction 4931 1451 57 covers neutron energy range from threshold of 9.228 MeV 4931 1451 58 ( including the energy of isomeric state which has 4931 1451 59 0.190 MeV ) to 20 MeV. Experimental knowledge of the 4931 1451 60 115-In(n,2n) reaction cross sections is entirely based 4931 1451 61 on the results of activation measurements. There are 4931 1451 62 still no experimental results obtained by 4931 1451 63 direct-neutron-detection methods (such as scintillation 4931 1451 64 tank). For both the indium isotopes (115-In,0.957, 4931 1451 65 113-In,0.043), the primary activity 4931 1451 66 resulting from the (n,2n) process is due to the decay of 4931 1451 67 metastable state. The interaction with the primary isotope, 4931 1451 68 115-In, results in a metastable state in 114-In which 4931 1451 69 decays with 49.5d half-life by means of an E4 transition 4931 1451 70 to the ground state (1+) with a half-life of 71.9s. 4931 1451 71 The (n,2n) process also directly populates the ground state. 4931 1451 72 Seventeen sets of data available [1-18] were collected. 4931 1451 73 For the sake of comparison, all the experimental results were 4931 1451 74 adjusted by the unified nuclear parameters (including 4931 1451 75 intensity of r-line, half-life, branching ratio), 4931 1451 76 the reference cross section and the dependence of cross 4931 1451 77 section on energy which were taken from [Ref.1]. In several 4931 1451 78 cases, adjustments were made only for the dependence of cross 4931 1451 79 section on energy since some necessary parameters used in data 4931 1451 80 analysis were not given by the authors. 4931 1451 81 The evaluation was made as the following ways: 4931 1451 82 (1).At 14.7MeV neutron energy . 4931 1451 83 Based on the results measured by Ge(Li) detector,the 4931 1451 84 recommended cross section at 14.7 MeV is 1290 mb. 4931 1451 85 (2). For the neutron energy range from threshold to 20 MeV. 4931 1451 86 The recommended excitation function was obtained 4931 1451 87 by fitting the measured data with least-square method in the 4931 1451 88 neutron energy range of 10.4-20MeV and by extrapolating from 4931 1451 89 10.4MeV to 9.228MeV based on the physical trend and systematics 4931 1451 90 calculation. 4931 1451 91 Covariance matrix is given for the evaluated data considering all 4931 1451 92 adjusted factors. 4931 1451 93 References 4931 1451 94 1.Zhao Wenrong et al., CNDC-89014;INDC(CPR)-16, 1989 4931 1451 95 2.Ke Wei et al., Chin.J.Nucl.Phys.11, 3, 11(1989) 4931 1451 96 Lu Hanlin et al., INDC(CPR)-011/GI, P67(1988) 4931 1451 97 3.J.Csikai et al., INDC(NDS)-232/L, P45(1989) 4931 1451 98 4.Li Jiangwei et al., Chin.J.Nucl.Phys., 10, 1, 52(1988) 4931 1451 99 Wu Zhihua et al., 88MITO, P315(1988) 4931 1451 100 5.T.B.Ryves et al., J.Phys., G9, 1549(1983) 4931 1451 101 6.T.B.Ryves et al., J.Phys., G7, 115(1981) 4931 1451 102 7.A.Reggoug et al., 82Antwerp, P873(1982);NIMA, 227, 249(1984) 4931 1451 103 8.K.Kayashima et al., NEANDC(J)-61U, P94(1979) 4931 1451 104 9.D.C.Santry et al., Can.J.Phys., 54, 757(1976) 4931 1451 105 10.Lu Hanlin et al., At.Energy Sci.Technol., 2, 113(1975) 4931 1451 106 11.A.Paulsen et al., Atomkernenergie, 26, 34(1975) 4931 1451 107 12.J.K.Temperley et al., BRL-1491(1970) 4931 1451 108 13.R.C.Barrall et al., Nucl.Phys., A138, 387(1969) 4931 1451 109 14.R.C.Barrall et al., AFWL-TR-68-134(1969) 4931 1451 110 15.H.Rotzer, Nucl.Phys., A109, 694(1968);DWA176, 289(1968) 4931 1451 111 16.B.Minetti et al., Z.Physik., A217, 83(1968) 4931 1451 112 17.H.O.Menlove et al., Phys.Rev., 163, 1308(1967) 4931 1451 113 18.R.J.Prestwood et al., Phys.Rev., 121, 1438(1961) 4931 1451 114 19.T.Kozlowski et al., Acta.Phys.Pol., 33, 409(1968) 4931 1451 115 20.R.Prasad et al.,Nucl.Phys., A94, 476(1967) 4931 1451 116 and 88,349(1966). 4931 1451 117 21.W.Nagel, JNE, 20, 475(1966) 4931 1451 118 22.K.C.Garg et al.,IPA17, 525(1979) 4931 1451 119 23.G.N.Salaita et al., ANS, 16, 59(1973) 4931 1451 120 24.J.Janczyszyn et al., J.Radiational Chem., 14, 201(1973) 4931 1451 121 25.M.Bormann et al., EANDC(E)76u, 51(1967) 4931 1451 122 26.W.Grochulski et al., INR-1172(1970);INR-1197, 10(1970) 4931 1451 123 Acta.Phys.Pol., BI, 271(1970) 4931 1451 124 27.H.K.Vonach et al., 68WASH, 2, P885(1968) 4931 1451 125 28.Wang Zisheng et al., Research on the Covariances Matrix 4931 1451 126 of the Evaluation Data(to be published) 4931 1451 127 4931 1451 128 4931 1451 129 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451 130 49-IN-115 HEDL,ANL EVAL-MAR90 F.SCHMITTROTH,D.L.SMITH,S.CHIBA 4931 1451 131 DIST-JUN90 900329 4931 1451 132 ----ENDF/B-VI MATERIAL 4931 4931 1451 133 -----INCIDENT NEUTRON DATA 4931 1451 134 ------ENDF-6 FORMAT 4931 1451 135 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4931 1451 136 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451 137 4931 1451 138 IN-115(N,N')IN-115M DOSIMETRY REACTION 4931 1451 139 4931 1451 140 EVALUATED BY S.CHIBA AND D.L. SMITH, ANL, JANUARY 1990 4931 1451 141 4931 1451 142 PRODUCTION OF THE ISOMER IN-115M BY THE (N,N') PROCESS IS 4931 1451 143 ROUTINELY EMPLOYED FOR NEUTRON DOSIMETRY APPLICATIONS. THIS 4931 1451 144 ISOMER IS THE FIRST-EXCITED STATE OF THE ISOTOPE IN-115 (336 KEV 4931 1451 145 EXCITATION ENERGY). THE REACTION THRESHOLD ENERGY IS 339 KEV. 4931 1451 146 THE ISOTOPIC ABUNDANCE OF IN-115 IN NATURAL INDIUM IS 95.7 4931 1451 147 PERCENT. THE HALF LIFE OF IN-115M IS 4.486 HOURS. THE DECAY 4931 1451 148 MODES ARE - BETA MINUS (5 PERCENT) ISOMERIC TRANSITION (95.0 4931 1451 149 PERCENT). THE NUMBER OF DECAY 336-KEV GAMMA RAYS EMITTED PER 4931 1451 150 DISINTEGRATION OF IN-115M IS 0.459. 4931 1451 151 4931 1451 152 DOCUMENTATION FOR THIS EVALUATION IS PROVIDED BY A.B. SMITH ET 4931 1451 153 AL., REPORT ANL/NDM-115, ARGONNE NATIONAL LABORATORY (1990). 4931 1451 154 EVALUATED RESULTS FOR THIS REACTION ARE BASED ON EXPERIMENTAL 4931 1451 155 DATA. NUCLEAR MODEL CALCULATIONS WERE USED TO ESTIMATE THE CROSS 4931 1451 156 SECTION SHAPE NEAR THRESHOLD. THIS EVALUATION WAS CARRIED OUT 4931 1451 157 USING THE STATISTICAL LEAST-SQUARES METHOD. THE CODE GMA, AS 4931 1451 158 DEVELOPED BY W. POENITZ (1981) AND LATER REVISED BY M. SUGIMOTO 4931 1451 159 (1987) AND S. CHIBA (1990), WAS EMPLOYED FOR THIS ANALYSIS. 4931 1451 160 4931 1451 161 * * * * * * *4931 1451 162 CAPTURE TO 54 MIN. ISOMERIC STATE DESCRIPTION MODIFIED BY 4931 1451 163 R. SCHENTER ON 2/20/84. THIS WAS DONE BY ADDING FILE9 WITH 4931 1451 164 Y=.79 AND PUTTING THE TOTAL CAPTURE WIDTH IN FILE2 AND THE TOTAL 4931 1451 165 CAPTURE CROSS SECTION IN FILE3. 4931 1451 166 P.C.TO NORMALIZATION+STANDARDS SUBCOMITTEE (N,N')D.L.SMITH MT=51 4931 1451 167 P.C.TO NORMALIZATION+STANDARDS SUBCOMITTEE (N,G)F.SCHMITTROTH 4931 1451 168 MF=2 MT=151 4931 1451 169 MF=2 MT=102 4931 1451 170 * * * * * 4931 1451 171 4931 1451 172 FILE INFORMATION 4931 1451 173 4931 1451 174 MF=1 MT=451 ATOMIC MASS FROM REF(1). 4931 1451 175 4931 1451 176 MF=2 MT=151 EVALUATION OF RESOLVED RESONANCE PARAMETERS 4931 1451 177 BASED ON NEW BNL-325, REF(2). 4931 1451 178 4931 1451 179 MF=3 MT= 51 EVALUATION OF THE 4.486 H ISOMER BASED ENTIRELY ON 4931 1451 180 REPORTED EXPERIMENTAL DATA.DOCUMENTATION AVAILABLE 4931 1451 181 AS ANL/NDM-26 BY D.L.SMITH REFERENCES 4931 1451 182 USED LISTED BELOW 10 TO 25. 4931 1451 183 MF=3 MT=102 VERSION-V UNRESOLVED REGION CONTAINS ADJUSTED DATA 4931 1451 184 SEE DOCUMENTATION 4931 1451 185 RADIATIVE NEUTRON CAPTURE TO THE IN 116M(54 MIN.) 4931 1451 186 STATE. 4931 1451 187 E GREATER THAN EH, 4931 1451 188 EVALUATION BASED ON EXPERIMENTAL DATA, REF.(3-7) 4931 1451 189 AND THEORETICAL CALCULATIONS, REF.(8,9). 4931 1451 190 E LESS THAT EH, 4931 1451 191 A 1/V COMPONENT WAS ADDED TO GIVE THE CORRECT 4931 1451 192 2200M/S CROSS SECTION TO THE 54 MIN. STATE(THE 4931 1451 193 2.2 SEC. STATE CROSS SECTION WAS INCLUDED). 4931 1451 194 RADIATIVE CAPTURE TO THE 2.2 SEC. STATE OF IN 116 WAS 4931 1451 195 INCLUDED AS PART OF THE CAPTURE TO THE 54 MIN. STATE 4931 1451 196 FOR BOTH THERMAL AND FAST ENERGIES. 4931 1451 197 RESULTS WERE DIVIDED BY .79 TO GIVE THE TOTAL CAP- 4931 1451 198 TURE CROSS SECTION IN FILE3. FILE9 COMBINED WITH 4931 1451 199 FILE3 IS REQUIRED TO GIVE CAPTURE TO 54 MIN. 4931 1451 200 ISOMERIC STATE. 4931 1451 201 4931 1451 202 2200M/S CAPTURE CROSS SECTION,BARNS TO THE 54 MIN. STATE 4931 1451 203 (FROM RESONANCE PARAMETERS) = 166.413 4931 1451 204 4931 1451 205 COMPUTED RESONANCE INTEGRAL =2587.345 4931 1451 206 4931 1451 207 REFERENCES. 4931 1451 208 1. A.H.WAPSTRA AND N.B.GOVE,NUCL. DATA TABLES,VOL.9,PART 1(1971).4931 1451 209 2. S.F.MUGHABGHAB AND D.I.GARBER,BNL-325,3RD ED.,VOL.1(1973) 4931 1451 210 3. H.A.GRENCH AND H.O.MENLOVE,PHYS.REV.,VOL.165(1968)1298. 4931 1451 211 4. H.O.MENLOVE,ET AL.,PHYS.REV.,VOL.163(1967)1299. 4931 1451 212 5. S.A.COX, PHYS.REV.,VOL.133(1964)B378. 4931 1451 213 6. A.E.JOHNSRUD,ET AL.,PHYS.REV.,VOL.116(1959)927. 4931 1451 214 7. G.PETO ET AL., J.NUCL.EN.,VOL.21(1967)797. 4931 1451 215 8. F.SCHMITTROTH, HEDL-TME 71-106(AUGUST 1971). 4931 1451 216 9. F.SCHMITTROTH, HEDL-TME 73-79,ENDF-195(NOVEMBER 1973). 4931 1451 217 10. D.L.SMITH ET.AL. ANL/NDM-14,1975 4931 1451 218 11. D.C.SANTRY AND J.P.BUTLER CAN.J.PHYS.54,757,1975 4931 1451 219 12. K.KOBAYASHI ET.AL. J.NUC.EN.27,741,73 4931 1451 220 13. A.PASZIT AND J.CSIKAI SOV.J.NUC.PHYS.15,232,1972 4931 1451 221 14. J.K.TEMPERLY AND D.E.BARNES BRL-1491,1970 4931 1451 222 15. P.DECOWSKI ET.AL.INR-1197 POLAND 1970 4931 1451 223 16. I.KIMURA ET.AL. J.NUC.SCI.TECH.JAP.6,485,69 4931 1451 224 17. R.C.BARRALL ET.AL. AFWL-TR-68-134,1969 4931 1451 225 18. H.ROETZER NUC.PHYS.A109,694,1968 4931 1451 226 19. B.MINETTI AND A.PAQUARETTI Z.PHYS.217,83,1968 4931 1451 227 20. H.A.GRENCH AND H.O.MENLOVE PHYS.REV.165,1298,1968 4931 1451 228 21. H.O.MENLOVE ET.AL. PHYS.REV.163,1308,1967 4931 1451 229 22. W.NAGEL AND A.H.W.ATEN JR. PHYSICA 31,1091,1965 4931 1451 230 23. A.A.ABEL AND C.GOODMAN PHYS.REV.93,197,1954 4931 1451 231 24. H.C.MARTIN AND B.C.DIVEN PHYS.REV.93,199,1954 4931 1451 232 25. S.G.COHEN NATURE 161,475,1948 4931 1451 233 4931 1451 234 ***************** PROGRAM LINEAR (VERSION 89-1) *****************4931 1451 235 DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.100 PER-CENT 4931 1451 236 **************** PROGRAM GROUPIE (VERSION 89-1) *****************4931 1451 237 UNSHIELDED GROUP AVERAGES USING 640 GROUPS (SAND-II EXTEND) 4931 1451 238 FLAT WEIGHTING SPECTRUM 4931 1451 239 1 451 248 14931 1451 240 2 151 145 14931 1451 241 3 16 39 14931 1451 242 3 51 75 14931 1451 243 3 102 217 14931 1451 244 33 16 23 14931 1451 245 33 51 86 14931 1451 246 33 102 6 14931 1451 247 4931 1 099999 4931 0 0 0 4.91150+ 4 1.139200+2 0 0 1 04931 2151 1 4.911500+4 1.000000+0 0 0 1 04931 2151 2 1.000000-5 1.003800+3 1 1 0 04931 2151 3 4.500000+0 6.500000-1 0 0 2 04931 2151 4 1.139200+2 0.000000+0 0 0 534 894931 2151 5 1.457000+0 5.000000+0 7.503600-2 3.036400-3 7.200000-2 0.000000+04931 2151 6 3.860000+0 4.000000+0 8.135400-2 3.544400-4 8.100000-2 0.000000+04931 2151 7 9.120000+0 5.000000+0 8.157300-2 1.572700-3 8.000000-2 0.000000+04931 2151 8 1.210000+1 4.500000+0 1.401100-1 1.120000-4 1.400000-1 0.000000+04931 2151 9 2.273000+1 4.500000+0 8.204000-2 1.040000-3 8.100000-2 0.000000+04931 2151 10 2.300000+1 4.500000+0 8.088000-2 1.180000-3 7.970000-2 0.000000+04931 2151 11 3.960000+1 4.500000+0 8.000000-2 4.000000-3 7.600000-2 0.000000+04931 2151 12 4.636000+1 4.500000+0 7.996000-2 2.600000-4 7.970000-2 0.000000+04931 2151 13 4.814000+1 4.500000+0 9.060000-2 6.000000-4 9.000000-2 0.000000+04931 2151 14 6.300000+1 4.500000+0 9.584000-2 8.400000-4 9.500000-2 0.000000+04931 2151 15 6.950000+1 4.500000+0 8.010000-2 4.000000-4 7.970000-2 0.000000+04931 2151 16 8.087000+1 4.500000+0 7.150000-2 1.500000-3 7.000000-2 0.000000+04931 2151 17 8.328000+1 4.500000+0 7.960000-2 6.600000-3 7.300000-2 0.000000+04931 2151 18 9.434000+1 4.500000+0 9.290000-2 2.900000-3 9.000000-2 0.000000+04931 2151 19 1.258900+2 4.500000+0 6.880000-2 3.800000-3 6.500000-2 0.000000+04931 2151 20 1.328100+2 4.500000+0 1.854000-1 5.400000-3 1.800000-1 0.000000+04931 2151 21 1.502900+2 4.500000+0 8.960000-2 4.600000-3 8.500000-2 0.000000+04931 2151 22 1.646700+2 4.500000+0 1.000000-1 1.800000-2 8.200000-2 0.000000+04931 2151 23 1.680800+2 4.500000+0 8.180000-2 2.100000-3 7.970000-2 0.000000+04931 2151 24 1.779200+2 4.500000+0 8.300000-2 3.000000-3 8.000000-2 0.000000+04931 2151 25 1.869600+2 4.500000+0 1.200000-1 2.000000-2 1.000000-1 0.000000+04931 2151 26 2.056000+2 4.500000+0 1.027000-1 2.300000-2 7.970000-2 0.000000+04931 2151 27 2.118800+2 4.500000+0 8.022000-2 5.200000-4 7.970000-2 0.000000+04931 2151 28 2.240300+2 4.500000+0 9.200000-2 3.200000-2 6.000000-2 0.000000+04931 2151 29 2.268100+2 4.500000+0 8.102000-2 1.320000-3 7.970000-2 0.000000+04931 2151 30 2.501700+2 4.500000+0 1.450000-1 6.000000-2 8.500000-2 0.000000+04931 2151 31 2.669600+2 4.500000+0 8.370000-2 4.000000-3 7.970000-2 0.000000+04931 2151 32 2.888800+2 4.500000+0 9.970000-2 2.000000-2 7.970000-2 0.000000+04931 2151 33 2.943300+2 4.500000+0 1.237000-1 4.400000-2 7.970000-2 0.000000+04931 2151 34 3.194900+2 4.500000+0 9.470000-2 1.500000-2 7.970000-2 0.000000+04931 2151 35 3.398000+2 4.500000+0 8.160000-2 1.900000-3 7.970000-2 0.000000+04931 2151 36 3.541300+2 4.500000+0 8.598000-2 6.280000-3 7.970000-2 0.000000+04931 2151 37 3.621000+2 4.500000+0 9.058000-2 1.088000-2 7.970000-2 0.000000+04931 2151 38 3.709400+2 4.500000+0 8.660000-2 6.900000-3 7.970000-2 0.000000+04931 2151 39 3.829700+2 4.500000+0 8.092000-2 1.220000-3 7.970000-2 0.000000+04931 2151 40 3.842000+2 4.500000+0 8.556000-2 5.860000-3 7.970000-2 0.000000+04931 2151 41 4.023500+2 4.500000+0 1.111000-1 3.140000-2 7.970000-2 0.000000+04931 2151 42 4.115600+2 4.500000+0 1.111000-1 3.140000-2 7.970000-2 0.000000+04931 2151 43 4.230000+2 4.500000+0 9.016000-2 1.046000-2 7.970000-2 0.000000+04931 2151 44 4.371600+2 4.500000+0 8.074000-2 1.040000-3 7.970000-2 0.000000+04931 2151 45 4.489000+2 4.500000+0 9.224000-2 1.254000-2 7.970000-2 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