Retrieved by E4-util: 2010/02/01,11:41:24 1 0 0 0 2.00300+03 2.99012+00 0 0 59 0 203 1451 1 0.00000+00 0.00000+00 0 0 0 6 203 1451 2 1.00000+00 2.00000+07 0 0 10 0 203 1451 3 0.00000+00 0.00000+00 0 0 205 15 203 1451 4 2-He- 3 IPPE EVAL-DEC05 NIKOLAEV M.N. 203 1451 5 DIST-DEC06 203 1451 6 ----RUSFOND MATERIAL 203 203 1451 7 -----INCIDENT NEUTRON DATA 203 1451 8 ------CONTENT: NEUTRON TRANSPORT 203 1451 9 -------ENDF-6 FORMAT 203 1451 10 ****************************************************************** 203 1451 11 Data from FOND-2.2 are preserved with the next changes 203 1451 12 203 1451 13 1.Capture cross section increased at high energies on the basis of 203 1451 14 new experimental data. 203 1451 15 2.Cross section of (n,d) reaction is slightly increased. 203 1451 16 3.Total cross section above 15 MeV is slightly lovered. 203 1451 17 4.Cross sections of (n,n'p) and (n,2n2p) reactions are lovered 203 1451 18 correspondingly. 203 1451 19 5.Reaction energies and thresholds are corrected according to 203 1451 20 2003 Wapstra data. 203 1451 21 6.MT=251, 252 and 253 are omitted in the file MF=3. 203 1451 22 7.File MF=8 omitted. 203 1451 23 8.Small inaccuracies in the cross section representation are 203 1451 24 removed 203 1451 25 203 1451 26 SEE RUSFOND MANUAL FOR DETAILS 203 1451 27 203 1451 28 ****************************************************************** 203 1451 29 203 1451 30 FOND-2.2 DESCRIPTION (Eval - Nikolaev M.N.) 203 1451 31 *********************** 203 1451 32 MF = 1 GENERAL INFORMATION: 203 1451 33 203 1451 34 MT = 451 COMMENTS ON EVALUATIONS, DICTIONARY AND 203 1451 35 REFERENCES. 203 1451 36 203 1451 37 M.N.NIKOLAEV ET AL. [1] EVALUATION THOROUGHLY 203 1451 38 REVISED WITH ACCOUNT OF NEW EXPERIMENTAL 203 1451 39 DATA. 203 1451 40 203 1451 41 ACCURACY OF THE HE-3 NEUTRON DATA SATISFIES 203 1451 42 TO THE NUCLEAR TECHNOLOGY 203 1451 43 REQUIREMENTS 203 1451 44 203 1451 45 (N,P) REACTION C.-S. IS RECOMMENDED TO 203 1451 46 USE AS A STANDARD FOR NEUTRON C.-S. 203 1451 47 MEASUREMENTS 203 1451 48 BELOW 50 KEV 203 1451 49 203 1451 50 THERE ARE NO PHOTONS IN NEUTRON INDUCED 203 1451 51 REACTIONS FOR HE-3 203 1451 52 203 1451 53 ------------------------------------------- 203 1451 54 0.0253 EV C.-S. 203 1451 55 SCATTERING (MT=2) - (3.16 +- 0.1) BARN 203 1451 56 RAD.CAPTURE (MT=102) - (25 +- 5) MICROBARN 203 1451 57 (N,P) REACTION (MT=103) - (5333 +- 7) BARN 203 1451 58 ------------------------------------------ 203 1451 59 203 1451 60 MF = 2 RESONANCE PARAMETERS: 203 1451 61 203 1451 62 MT = 151 AVERAGE SCATTERING LENGTH IS GIVEN: 203 1451 63 203 1451 64 A = r(1/4) + (A + B + 3A)) = 203 1451 65 203 1451 66 = 5.015 FERMI = 0.5015*10 CM. 203 1451 67 203 1451 68 A = 6.484 FERMI - REAL PART OF SINGLET 203 1451 69 SCATTERING AMPLITUDE; 203 1451 70 203 1451 71 B = 4.4475 FERMI - IMAGINARY PART OF 203 1451 72 SINGLET SCATTERING AMPLITUDE; 203 1451 73 203 1451 74 A = 3.595 FERMI - REAL PART OF TRIPLET 203 1451 75 SCATTERING AMPLITUDE. B =0 203 1451 76 203 1451 77 DATA GIVEN ARE BASED ON PHASE ANALYSIS 203 1451 78 PERFORMED IN REF.[2], WITH SMALL 203 1451 79 CORRECTIONS FOR CONSISTENCY WITH TAKEN 203 1451 80 (N,P) REACTION C.-S. IN THERMAL REGION: 203 1451 81 203 1451 82 B = K * S / 3.1416, 203 1451 83 WHERE K IS A NEUTRON WAVE NUMBER. 203 1451 84 203 1451 85 MF = 3 NEUTRON CROSS-SECTIONS: 203 1451 86 203 1451 87 MT = 1 SUM OF PARTIAL C.-S. 203 1451 88 203 1451 89 MT = 2 ELASTIC SCATTERING C.-S. IS CALCULATED UP TO 203 1451 90 200 KEV AS: 203 1451 91 203 1451 92 S = 3.1416 * ((A+B)/(1+K*B)+K*A)+ 203 1451 93 + (3*A/((1+ K)*A)), 203 1451 94 203 1451 95 WHERE 203 1451 96 K = 2.1968 * 10 * (AWR/(1+AWR)) * SQRT(E), 203 1451 97 A , B , A - IN UNITS OF 10 CM. 203 1451 98 203 1451 99 ELASTIC SCATTERING C.-S. FOR E > 200 KEV IS 203 1451 100 BASED ON DATA BY HAESNER ET AL. [3] CONFIRMED 203 1451 101 BY OTHER (SEE M.DROGS ET AL. [4]). 203 1451 102 203 1451 103 MT = 16 HE-3(N,2N+2P) REACTION C.-S. TILL NOW WAS 203 1451 104 NOT DETERMINED ACCURATELY. THIS REACTION 203 1451 105 C.-S. WAS TAKEN AS LINEAR DEPENDENT WITH 203 1451 106 ENERGY FROM 0 AT THRESHOLD ENERGY (10.2994 203 1451 107 MEV) TO 10 MBARN AT 20. MEV. 14-MEV C.-S. 203 1451 108 VALUE (3 MBARN) DOES NOT CONTRADICT TO THE 203 1451 109 AVAILABLE EXPERIMENTAL DATA REF.[5,6]. 203 1451 110 203 1451 111 MT = 28 HE-3(N,N+P)D REACTION C.-S. IS EVALUATED 203 1451 112 TAKING INTO ACCOUNT DATA BY HAESNER ET AL. 203 1451 113 [3] AND M.DROSG ET AL. [4] WITHOUT SMALL 203 1451 114 CONTRIBUTION OF THE HE-3(N,2N+2P) REACTION 203 1451 115 WITH THRESHOLD 7.3308 MEV. 203 1451 116 203 1451 117 MT = 102 RADIATIVE CAPTURE C.-S. IS EVALUATED TAKING 203 1451 118 ACCOUNT DATA BY V.P.ALFIMENKOV ET AL. 203 1451 119 REF.[7,8] FOR ENERGIES LESS THAN 0.4 EV AND 203 1451 120 WITH 1/V C.-S. ENERGY DEPENDENCE.THE SAME 203 1451 121 ENERGY DEPENDENCE IS TRUE FOR ENERGIES 203 1451 122 BETWEEN 1.5 KEV - 50 KEV, WHERE ALSO A 203 1451 123 CONTRIBUTION OF P-WAVE IS IMPORTANT. THE 203 1451 124 C.-S. IS SMOOTHLY CONJUGATE WITH DATA BY 203 1451 125 L.VARD ET AL. [9], OBTAINED FOR E=16-18 MEV 203 1451 126 UNDER 90 DEG ANGLE. TOTAL REACTION C.-S. WAS 203 1451 127 EVALUATED ASSUMING THE ISOTROPIC GAMMA 203 1451 128 EMISSION. 203 1451 129 203 1451 130 MT = 103 HE-3(N,P)T REACTION C.-S. IS RECOMMENDED AS 203 1451 131 STANDARD FOR NEUTRON C.-S. MEASUREMENTS FOR 203 1451 132 ENERGIES BELOW 50. KEV. THE C.-S. WAS 203 1451 133 CALCULATED FOR ENERGIES BELOW 1 KEV AS: 203 1451 134 203 1451 135 S = 3.1416 * B/K/((1+K*B)+(K*A)) 203 1451 136 203 1451 137 WITH THE PARAMETERS A = 0.06486, B = 0.4447 203 1451 138 (IN UNITS OF 10)CM). IT GIVES S (0.0253 EV) 203 1451 139 = 5333 BARN. 203 1451 140 203 1451 141 ENDF/B-6 VALUES ARE RECOMMENDED BETWEEN 1 KEV 203 1451 142 AND 50 KEV. THE VALUE 5316 EV AT EN=0.0253 203 1451 143 BARN WAS RECOMMENDED BY ENDF/B-6. THE C.-S. 203 1451 144 CALCULATED ON GIVEN ABOVE FORMULAS ARE 203 1451 145 COINCIDE WITH ENDF/B-6 VALUES. THE C.-S. IS 203 1451 146 DECREASING SMOOTHLY BETWEEN 50 KEV AND 900 203 1451 147 KEV, REACHING THE MINIMUM VALUE 0.813 BARN AT 203 1451 148 900 KEV. IT IS AT 7% BELOW ENDF/B-5 203 1451 149 RECOMMENDATIONS AND DATA [1]. 203 1451 150 THEN THE C.-S. IS RAISING UP, REACHING 203 1451 151 MAXIMUM AT EN=1.6 MEV AND COINCIDING WITH 203 1451 152 DATA RECOMMENDED EARLIER /1/. THIS PREVIOUS 203 1451 153 RECOMMENDATION WAS TAKEN FOR ENERGIES BETWEEN 203 1451 154 1.6 AND 7 MEV. THE C.-S. VALUES AT 10% HIGHER 203 1451 155 THEN IN PREVIOUS RECOMMENDATION ARE TAKEN AT 203 1451 156 PRESENT. 203 1451 157 203 1451 158 MT = 104 HE-3(N,D) REACTION C.-S. (ENERGY THRESHOLD 203 1451 159 4.3622 MEV) WAS TAKEN ACCORDING DATA HAESNER 203 1451 160 ET AL. [3]. 203 1451 161 203 1451 162 MT = 251, 252, 253 WERE OBTAINED FROM ELASTIC 203 1451 163 SCATTERING ANGULAR DISTRIBUTIONS. 203 1451 164 (In RUSFOND these data are omited) 203 1451 165 MF = 4 ANGULAR DISTRIBUTIONS: 203 1451 166 203 1451 167 MT = 2 ELASTIC SCATTERING ANGULAR DISTRIBUTIONS ARE 203 1451 168 GIVEN BY LEGENDRE POLYNOMIAL COEFFICIENTS IN 203 1451 169 CMS ON THE BASIS OF DATA BY HAESNER ET AL. 203 1451 170 [3]. 203 1451 171 203 1451 172 MF = 6 MT = 16 ENERGY-ANGULAR DISTRIBUTIONS OF THE 203 1451 173 HE-3(N,2+2P) REACTION PRODUCTS ARE GIVEN BY 203 1451 174 LAW=6. 203 1451 175 203 1451 176 MT = 28 ENERGY-ANGULAR DISTRIBUTIONS OF THE 203 1451 177 HE-3(N,NP)D REACTION PRODUCTS ARE DESCRIBED 203 1451 178 BY LAW=6. THERE ARE SOME EXPERIMENTAL DATA 203 1451 179 SHOWING A SUBSTANTIAL CONTRIBUTION OF THE 203 1451 180 DIRECT PROCESSES AT FORWARD ANGLES (SEE 203 1451 181 [5]). 203 1451 182 203 1451 183 MT = 102, 103, 104 ARE ISOTROPIC IN CMS WITH ENERGY 203 1451 184 DISTRIBUTIONS OF THE REACTION PRODUCTS AS 203 1451 185 DELTA-FUNCTIONS. 203 1451 186 203 1451 187 MF = 8 MT = 103 DATA ON DECAY OF TRITIUM FORMED IN 203 1451 188 HE-3(N,P) REACTION ARE GIVEN. 203 1451 189 (In RUSFOND these data are omited) 203 1451 190 REFERENCES. 203 1451 191 203 1451 192 1. NIKOLAEV M.N. ET AL. EVALUATED NEUTRON C.-S. FILES IN 203 1451 193 SOKRATOR LIBRARY, REVIEW, OBNINSK, FEI, 1977. 203 1451 194 2. ALFIMENKOV V.P. ET AL. YADERNAY FIZIKA, 33(4), 1981, 203 1451 195 P.891 203 1451 196 3. HAESNERR ET AL. EXFOR 21883 (1982). 203 1451 197 4. DROSG M. ET AL(1974) EXFOR 10425. 203 1451 198 5. ANTOLKOVIC B. ET AL PHYS. LETT, 23, 477(1966), EXFOR 203 1451 199 30043. 203 1451 200 6. MATHER D.S., PAIN L.F. (1966) EXFOR 20794.004. 203 1451 201 7. ALFIMENKOV V.P. ET AL. YADERNAY FIZIKA, 31(1), 1981, 203 1451 202 P.21 203 1451 203 8. PICKELNER L.B. ET AL., USPEKHI FIZ. NAUK, 137, 1982, 203 1451 204 P.38 203 1451 205 9. WARD L. ET AL. PR/C 24, 317(1981) EXFOR 12707. 203 1451 206 203 1451 207 ************************ C O N T E N T *************************** 203 1451 208 (MF) (MT) (CARDS) 203 1451 209 1 451 224 0 203 1451 210 2 151 4 0 203 1451 211 3 1 22 0 203 1451 212 3 2 22 0 203 1451 213 3 16 4 0 203 1451 214 3 28 7 0 203 1451 215 3 102 22 0 203 1451 216 3 103 22 0 203 1451 217 3 104 9 0 203 1451 218 4 2 110 0 203 1451 219 6 16 9 0 203 1451 220 6 28 13 0 203 1451 221 6 102 31 0 203 1451 222 6 103 19 0 203 1451 223 6 104 10 0 203 1451 224 203 1 099999 203 0 0 0 2.00300+03 2.99012+00 0 0 1 0 203 2151 1 2.00300+03 1.00000+00 0 0 1 0 203 2151 2 1.00000-05 2.00000+07 0 0 0 0 203 2151 3 5.00000-01 2.82100-01 0 0 0 0 203 2151 4 203 2 099999 203 0 0 0 2.00300+ 3 2.99012+ 0 0 0 0 0 203 3 1 1 0.00000+ 0 0.00000+ 0 0 0 1 57 203 3 1 2 57 2 203 3 1 3 1.000000-5 2.682481+5 2.530000-2 5.336160+3 1.000000+1 2.713963+2 203 3 1 4 3.160000+1 1.540462+2 1.000000+2 8.795839+1 3.160000+2 5.083592+1 203 3 1 5 1.000000+3 2.989547+1 2.000000+3 2.077865+1 3.160000+3 1.688293+1 203 3 1 6 4.000000+3 1.521102+1 6.000000+3 1.272228+1 8.000000+3 1.124283+1 203 3 1 7 1.000000+4 1.022629+1 1.500000+4 8.661233+0 2.000000+4 7.718977+0 203 3 1 8 2.500000+4 7.068020+0 3.000000+4 6.580664+0 3.160000+4 6.447907+0 203 3 1 9 3.500000+4 6.195706+0 4.000000+4 5.879949+0 4.500000+4 5.613592+0 203 3 1 10 5.000000+4 5.383634+0 6.000000+4 5.026119+0 8.000000+4 4.582172+0 203 3 1 11 1.000000+5 4.258224+0 1.500000+5 3.764128+0 2.000000+5 3.460031+0 203 3 1 12 3.000000+5 3.190035+0 3.160000+5 3.166470+0 4.000000+5 3.066040+0 203 3 1 13 5.000000+5 3.010040+0 6.000000+5 3.005046+0 8.000000+5 2.988051+0 203 3 1 14 1.000000+6 3.010056+0 1.200000+6 3.096060+0 1.500000+6 3.204065+0 203 3 1 15 2.000000+6 3.270073+0 2.500000+6 3.190079+0 3.000000+6 3.030083+0 203 3 1 16 3.160000+6 2.969721+0 4.000000+6 2.697085+0 4.362150+6 2.589719+0 203 3 1 17 5.000000+6 2.438084+0 6.000000+6 2.213079+0 7.000000+6 1.995735+0 203 3 1 18 7.330689+6 1.931615+0 8.000000+6 1.805070+0 9.000000+6 1.655057+0 203 3 1 19 1.000000+7 1.528260+0 1.029923+7 1.497841+0 1.100000+7 1.428695+0 203 3 1 20 1.200000+7 1.332558+0 1.300000+7 1.244233+0 1.400000+7 1.158721+0 203 3 1 21 1.600000+7 1.035997+0 1.800000+7 9.297807-1 2.000000+7 8.550360-1 203 3 1 22 203 3 099999 2.00300+03 2.99012+00 0 0 0 0 203 3 2 1 0.00000+ 0 0.00000+ 0 0 0 1 57 203 3 2 2 57 2 203 3 2 3 1.000000-5 3.120260+0 2.530000-2 3.159820+0 1.000000+1 3.151290+0 203 3 2 4 3.160000+1 3.146636+0 1.000000+2 3.131900+0 3.160000+2 3.117277+0 203 3 2 5 1.000000+3 3.070970+0 2.000000+3 3.045650+0 3.160000+3 3.016279+0 203 3 2 6 4.000000+3 2.995010+0 6.000000+3 2.944370+0 8.000000+3 2.914025+0 203 3 2 7 1.000000+4 2.883680+0 1.500000+4 2.844922+0 2.000000+4 2.806164+0 203 3 2 8 2.500000+4 2.767406+0 3.000000+4 2.728648+0 3.160000+4 2.716245+0 203 3 2 9 3.500000+4 2.689890+0 4.000000+4 2.651132+0 4.500000+4 2.612374+0 203 3 2 10 5.000000+4 2.573616+0 6.000000+4 2.496100+0 8.000000+4 2.432150+0 203 3 2 11 1.000000+5 2.368200+0 1.500000+5 2.284100+0 2.000000+5 2.200000+0 203 3 2 12 3.000000+5 2.140000+0 3.160000+5 2.140000+0 4.000000+5 2.140000+0 203 3 2 13 5.000000+5 2.140000+0 6.000000+5 2.152000+0 8.000000+5 2.176000+0 203 3 2 14 1.000000+6 2.200000+0 1.200000+6 2.256000+0 1.500000+6 2.340000+0 203 3 2 15 2.000000+6 2.440000+0 2.500000+6 2.450000+0 3.000000+6 2.400000+0 203 3 2 16 3.160000+6 2.372800+0 4.000000+6 2.230000+0 4.362150+6 2.164811+0 203 3 2 17 5.000000+6 2.050000+0 6.000000+6 1.860000+0 7.000000+6 1.670000+0 203 3 2 18 7.330689+6 1.613764+0 8.000000+6 1.500000+0 9.000000+6 1.370000+0 203 3 2 19 1.000000+7 1.260000+0 1.029923+7 1.234551+0 1.100000+7 1.175000+0 203 3 2 20 1.200000+7 1.090000+0 1.300000+7 1.010000+0 1.400000+7 9.300000-1 203 3 2 21 1.600000+7 8.099999-1 1.800000+7 7.000000-1 2.000000+7 6.200000-1 203 3 2 22 203 3 099999 2.00300+03 2.99012+00 0 0 0 0 203 3 16 1 -7.718046+6-7.718046+6 0 0 1 2 203 3 16 2 2 2 203 3 16 3 1.029923+7 0.000000+0 2.000000+7 7.000000-3 203 3 16 4 203 3 099999 2.00300+03 2.99012+00 0 0 0 0 203 3 28 1 -5.493479+6-5.493479+6 0 0 1 12 203 3 28 2 12 2 203 3 28 3 7.330689+6 0.000000+0 8.000000+6 5.000000-4 9.000000+6 1.000000-3 203 3 28 4 1.000000+7 2.200000-3 1.029923+7 2.500000-3 1.100000+7 3.500000-3 203 3 28 5 1.200000+7 6.000000-3 1.300000+7 1.000000-2 1.400000+7 1.500000-2 203 3 28 6 1.600000+7 3.000000-2 1.800000+7 5.000000-2 2.000000+7 7.000000-2 203 3 28 7 203 3 099999 2.00300+03 2.99012+00 0 0 0 0 203 3102 1 2.057762+7 2.057762+7 0 0 2 57 203 3102 2 21 5 57 2 203 3102 3 1.000000-5 1.260000-6 2.530000-2 2.500000-5 1.000000+1 1.260000-6 203 3102 4 3.160000+1 1.100000-6 1.000000+2 1.500000-6 3.160000+2 2.400000-6 203 3102 5 1.000000+3 3.800000-6 2.000000+3 4.818519-6 3.160000+3 6.000000-6 203 3102 6 4.000000+3 6.491228-6 6.000000+3 7.660820-6 8.000000+3 8.830409-6 203 3102 7 1.000000+4 1.000000-5 1.500000+4 1.138889-5 2.000000+4 1.277778-5 203 3102 8 2.500000+4 1.416667-5 3.000000+4 1.555556-5 3.160000+4 1.600000-5 203 3102 9 3.500000+4 1.639766-5 4.000000+4 1.698246-5 4.500000+4 1.756725-5 203 3102 10 5.000000+4 1.815205-5 6.000000+4 1.932164-5 8.000000+4 2.166082-5 203 3102 11 1.000000+5 2.400000-5 1.500000+5 2.750000-5 2.000000+5 3.100000-5 203 3102 12 3.000000+5 3.500000-5 3.160000+5 3.564000-5 4.000000+5 3.900000-5 203 3102 13 5.000000+5 4.300000-5 6.000000+5 4.560000-5 8.000000+5 5.080000-5 203 3102 14 1.000000+6 5.600000-5 1.200000+6 5.960000-5 1.500000+6 6.500000-5 203 3102 15 2.000000+6 7.300001-5 2.500000+6 7.900000-5 3.000000+6 8.300000-5 203 3102 16 3.160000+6 8.332001-5 4.000000+6 8.500000-5 4.362150+6 8.463784-5 203 3102 17 5.000000+6 8.400001-5 6.000000+6 7.920000-5 7.000000+6 7.440000-5 203 3102 18 7.330689+6 7.281216-5 8.000000+6 6.960000-5 9.000000+6 6.480000-5 203 3102 19 1.000000+7 6.000000-5 1.029923+7 5.928144-5 1.100000+7 5.760000-5 203 3102 20 1.200000+7 5.520000-5 1.300000+7 5.280000-5 1.400000+7 5.040000-5 203 3102 21 1.600000+7 4.560000-5 1.800000+7 4.080000-5 2.000000+7 3.600000-5 203 3102 22 203 3 099999 2.00300+03 2.99012+00 0 0 0 0 203 3103 1 7.637556+5 7.637556+5 0 0 2 57 203 3103 2 21 5 57 2 203 3103 3 1.000000-5 2.682450+5 2.530000-2 5.333000+3 1.000000+1 2.682450+2 203 3103 4 3.160000+1 1.508996+2 1.000000+2 8.482650+1 3.160000+2 4.771864+1 203 3103 5 1.000000+3 2.682450+1 2.000000+3 1.773300+1 3.160000+3 1.386664+1 203 3103 6 4.000000+3 1.221600+1 6.000000+3 9.777900+0 8.000000+3 8.328800+0 203 3103 7 1.000000+4 7.342600+0 1.500000+4 5.816300+0 2.000000+4 4.912800+0 203 3103 8 2.500000+4 4.300600+0 3.000000+4 3.852000+0 3.160000+4 3.731645+0 203 3103 9 3.500000+4 3.505800+0 4.000000+4 3.228800+0 4.500000+4 3.001200+0 203 3103 10 5.000000+4 2.810000+0 6.000000+4 2.530000+0 8.000000+4 2.150000+0 203 3103 11 1.000000+5 1.890000+0 1.500000+5 1.480000+0 2.000000+5 1.260000+0 203 3103 12 3.000000+5 1.050000+0 3.160000+5 1.026435+0 4.000000+5 9.260000-1 203 3103 13 5.000000+5 8.700000-1 6.000000+5 8.530000-1 8.000000+5 8.120000-1 203 3103 14 1.000000+6 8.099999-1 1.200000+6 8.400000-1 1.500000+6 8.640000-1 203 3103 15 2.000000+6 8.299999-1 2.500000+6 7.400000-1 3.000000+6 6.300000-1 203 3103 16 3.160000+6 5.968378-1 4.000000+6 4.670000-1 4.362150+6 4.248233-1 203 3103 17 5.000000+6 3.660000-1 6.000000+6 3.090000-1 7.000000+6 2.686609-1 203 3103 18 7.330689+6 2.576358-1 8.000000+6 2.380000-1 9.000000+6 2.124921-1 203 3103 19 1.000000+7 1.920000-1 1.029923+7 1.862819-1 1.100000+7 1.741322-1 203 3103 20 1.200000+7 1.592761-1 1.300000+7 1.467317-1 1.400000+7 1.360000-1 203 3103 21 1.600000+7 1.198374-1 1.800000+7 1.071831-1 2.000000+7 9.700001-2 203 3103 22 203 3 099999 2.00300+03 2.99012+00 0 0 0 0 203 3104 1 -3.268912+6-3.268912+6 0 0 1 16 203 3104 2 16 2 203 3104 3 4.362150+6 0.000000+0 5.000000+6 2.200000-2 6.000000+6 4.400000-2 203 3104 4 7.000000+6 5.700000-2 7.330689+6 6.014260-2 8.000000+6 6.650000-2 203 3104 5 9.000000+6 7.150001-2 1.000000+7 7.400000-2 1.029923+7 7.444910-2 203 3104 6 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