IRDF-2002 separated 02.07.09 from irdf-2002-g_n.dat .901900E+04 1.88352E+1 0 0 34 10 925 1451 1 0.0 0.0 0 0 0 6 925 1451 2 1.00000E+0 3.00001E+7 0 0 10 2002 925 1451 3 3.00000E+2 0.0 1 0 164 4 925 1451 4 9-F - 19 FEI EVAL-OCT01 K.I.Zolotarev 925 1451 5 DIST-Feb2004 925 1451 6 ----IRDF-2002 MATERIAL 925 925 1451 7 -----INCIDENT NEUTRON DATA 925 1451 8 ------ENDF-6 FORMAT 925 1451 9 ***************************************************************** 925 1451 10 9-F -19 FEI EVAL-OCT01 K.I.Zolotarev 925 1451 11 DIST-JAN02 20020125 925 1451 12 ----BROND-2 MATERIAL 925 925 1451 13 -----INCIDENT NEUTRON DATA 925 1451 14 ------ENDF-6 FORMAT 925 1451 15 ------Russian Reactor Dosimetry File RRDF-2002 925 1451 16 ***************************************************************** 925 1451 17 Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko 925 1451 18 ***************************************************************** 925 1451 19 MF= 3 925 1451 20 MT= 16 -(n,2n) cross section data 925 1451 21 -------------------------------------- 925 1451 22 Excitation function for the F-19(n,2n)F-18 reaction in the 925 1451 23 energy region from threshold to 30 MeV was evaluated by means of 925 1451 24 statistical analysis of experimental cross section data [1-17] and 925 1451 25 data from GNASH [18,19] calculation. 925 1451 26 Experimental data [2-3],[5],[9-13],[15-17] were renormalized 925 1451 27 to the new standards for monitor reactions cross sections. Data 925 1451 28 of Mc Crary et al. [1], Rayburn et al.[2], Bormann et al.[4], and 925 1451 29 Shiokawa et al. [7] were renormalized to the results of precise 925 1451 30 measurements Vonach et al. [9] and Ikeda et al. [15] in the 14 MeV 925 1451 31 region. Data of Chatterjee et al. [8] were corrected to their pre- 925 1451 32 vious measurements at the 14.8 MeV point [6]. Results of measure- 925 1451 33 ments of Nagel [5] were taken only from SUBENT 005, EXFOR 20198. 925 1451 34 Experimental cross section data from ref. [20-31] were rejec- 925 1451 35 ted due to their big discrepancy with the main bulk of experimen- 925 1451 36 al data [1-17] and data from theoretical model calculation. 925 1451 37 The final procedure of evaluation F-19(n,2n)F-18 excitation 925 1451 38 function from threshold to 30 MeV has been carried out within the 925 1451 39 framework of generalized least squares method. Rational function 925 1451 40 was used as model function [32]. Calculations was performed by 925 1451 41 means of Pade-2 code [33]. 925 1451 42 U-235 thermal fission [34] and Cf-252 spontaneous fission 925 1451 43 neutron spectra [35] averaged cross-sections calculated from the 925 1451 44 evaluated F-19(n,2n)F-18 excitation function are the following: 925 1451 45 925 1451 46 ----------------------------------------------------------------- 925 1451 47 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 925 1451 48 ----------------------I-----------------I------------------------ 925 1451 49 U-235 neutron fission I 0.007299 I 0.007200+-0.001000 [36] 925 1451 50 I I 0.006509+-0.000300 [37] 925 1451 51 I I 0.008653+-0.000464 [38] 925 1451 52 ----------------------I-----------------I------------------------ 925 1451 53 CF-252 spont. fission I 0.01615 I 0.01628+-0.00054 [39] 925 1451 54 I I 0.01612+-0.00054 [40] 925 1451 55 ----------------------------------------------------------------- 925 1451 56 925 1451 57 MF=33 925 1451 58 MT= 16 -(n,2n) cross section cov. matrix 925 1451 59 --------------------------------------------- 925 1451 60 Uncertainties in the evaluated excitation function for the 925 1451 61 reaction F-19(n,2n)F-18 are given in the form of relative covari- 925 1451 62 ance matrix for the 26-neutron energy groups (LB=5). Covariance 925 1451 63 matrix of uncertainties was calculated simultaneously with 925 1451 64 recommended cross section data by means of PADE-2 code. 925 1451 65 Eigenvalues of the 6-th digits relative covariance matrix 925 1451 66 given in the 33-file are the following: 925 1451 67 925 1451 68 3.67622E-08 3.74071E-08 3.79051E-08 3.91111E-08 925 1451 69 4.11094E-08 4.32321E-08 4.68199E-08 4.98738E-08 925 1451 70 5.55426E-08 6.01322E-08 7.00100E-08 7.85485E-08 925 1451 71 9.57150E-08 1.06820E-07 1.28694E-07 1.47868E-07 925 1451 72 2.58858E-07 6.32301E-07 3.80384E-06 5.45023E-04 925 1451 73 1.36448E-03 3.28506E-03 8.26671E-03 1.39754E-02 925 1451 74 1.58981E-02 6.37025E-02 925 1451 75 925 1451 76 References : 925 1451 77 1. J.H.Mc Crary,I.L.Morgan Bull. American Phys. Soc., v.5, 925 1451 78 p.246, April 1960 ; 925 1451 79 J.H.Mc Crary,I.L.Morgan Report AFSWC-TR-60-30, 1960 925 1451 80 2. L.A.Rayburn Proc. of Conf. on Direct Interactions and Nuclear 925 1451 81 Reaction Mechanisms, Padua, 3-8 September 1962, Gordon and 925 1451 82 Breach, New York, 1963, p.322. ; 925 1451 83 L.A.Rayburn Bull. Am. Phys. Soc., v.7, p.335, April 1962 925 1451 84 3. M.Cevolani, S.Petralia Nuovo Cimento, v.26, p.1328, Dec.1962 925 1451 85 4. M.Bormann et al. Nucl. Phys., v.63, p.438, March 1965 925 1451 86 5. W.Nagel EXFOR 20198.005, 1966 925 1451 87 6. A.Chatterjee et al. Progress Report BARC-305, p.30, Nov. 1967 925 1451 88 7. T.Shiokawa et al. J. Inorg. Nucl. Chem., v.30, p.1, Jan. 1968 925 1451 89 8. A.Chatterjee e.a. Proc.of Symposium Nucl.Phys. and Solid State 925 1451 90 Phys., Roorke, India, 1969, v.2, p.117, December 1969 925 1451 91 9. H.K.Vonach et al. Proc. of 2-nd Conference on Nuclear Cross- 925 1451 92 Sections and Technology, Washington D.C., 4-7 March 1968, v.2, 925 1451 93 p.885 925 1451 94 10. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 925 1451 95 11. R.Mogharrab, H.Neuert Atomkernenergie, v.19, p.107, April 1972 925 1451 96 12. J.C.Robertson et al. J. Nucl. Energ., v.27, p.531, Aug. 1973 925 1451 97 13. R.A.Sigg Dissert. Abstr., sect. B, v.37, p.2237, Nov. 1976 925 1451 98 14. T.B.Ryves et al. J. of Physics, pt.G, v.4, n.11, p.1783, 1978 925 1451 99 15. Y.Ikeda et al. Report JAERI-1312, 1988 925 1451 100 16. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v.106, p.332, 1990 925 1451 101 17. C.L.Hartmann, P.M.DeLuca Nucl. Sci. Eng., v.109, p.319, 1991 925 1451 102 18. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 925 1451 103 Model Code for Calculation of Cross Section and Emission 925 1451 104 Spectra. Report LA-6947, Los Alamos, 1977 925 1451 105 19. E.L.Trykov, G.Ya.Tertychnyi Private communication, IPPE, 925 1451 106 Obninsk, May 1999 925 1451 107 20. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31, p.267, 1953 925 1451 108 21. V.J.Ashby e.a. Phys. Rev., v.111, p.616, 1958 925 1451 109 22. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 925 1451 110 23. O.D.Brill et al. Doklady Akademii Nauk, v.136,n.1,p.55, 1961; 925 1451 111 O.D.Brill et al. Soviet Physics-Doklady, v.6, p.24, 1961 925 1451 112 24. J.Picard, C.F.Williamson Nucl. Phys., v.63, p.673, April 1965 925 1451 113 25. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 925 1451 114 26. J.Csikai Report EANDC-50 S, paper 102, July 1965 925 1451 115 27. A.Pasquarelli Nucl. Phys. A, v.93, p.218, March 1967 925 1451 116 28. M.Bormann, I.Riehle Zeitschrift f.Physik, v.207, p.64, 925 1451 117 October 1967 925 1451 118 29. H.O.Menlove et al. Phys. Rev., v.163, p.1308, 1967 925 1451 119 30. D.Crumpton J.Inorg. Nucl. Chem., v.31, p.3727, December 1969 925 1451 120 31. J.Araminowicz, J.Dresler Report INR-1464, p.14, May 1973 925 1451 121 32. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 925 1451 122 st's Meeting on Evaluation and Processing of Covariance Data, 925 1451 123 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 925 1451 124 33. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 925 1451 125 34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 925 1451 126 Library, MAT=9228, MF=5, MT=18, eval. April 1989 925 1451 127 35. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 925 1451 128 36. F.Nasyrov, B.D.Sciborskij Atomnaja Energija, v.25, no.5, 925 1451 129 p.437, November 1968 925 1451 130 37. M.Najzer, J.Rant Report IAEA-208, v.2, p.247, 1978 925 1451 131 38. W.Mannhart Progress Report INDC(Ger)-045, pp.40-43, 1999 925 1451 132 39. W.Mannhart Handbook on Nuclear Activation Data. IAEA Tech- 925 1451 133 nical Report series No.273, p.413, 1987 925 1451 134 40. W.Mannhart Validation of Differential Cross Sections with 925 1451 135 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 925 1451 136 September 2002 925 1451 137 ***************************************************************** 925 1451 138 File 2 added to the pointwise file containing only the effective 925 1451 139 scattering radius with no resonance parameters given. 925 1451 140 Taken from ENDF/B-VI 925 1451 141 925 1451 142 ***************************************************************** 925 1451 143 ***************** Program LINEAR (VERSION 2002-1) *************** 925 1451 144 For All Data Greater than 1.0000E-10 barns in Absolute Value 925 1451 145 Data Linearized to Within an Accuracy of .100000000 per-cent 925 1451 146 ***************** Program SIGMA1 (VERSION 2002-1) *************** 925 1451 147 Data Doppler Broadened to 300.000000 Kelvin 925 1451 148 for All Data Greater than 1.0000E-10 barns in Absolute Value 925 1451 149 Data Linearized to Within an Accuracy pf .100000000 per-cent 925 1451 150 ***************** Program FIXUP (Version 2002-1) **************** 925 1451 151 Corrected ZA/AWR in All Sections-----------------------------Yes 925 1451 152 Corrected Thresholds-----------------------------------------Yes 925 1451 153 Extended Cross Sections to 20 MeV----------------------------No 925 1451 154 Allow Cross Section Deletion---------------------------------No 925 1451 155 Allow Cross Section Reconstruction---------------------------No 925 1451 156 Make All Cross Sections Non-Negative-------------------------Yes 925 1451 157 Delete Energies Not in Ascending Order-----------------------Yes 925 1451 158 Deleted Duplicate Points-------------------------------------Yes 925 1451 159 Check for Ascending MAT/MF/MT Order--------------------------Yes 925 1451 160 Check for Legal MF/MT Numbers--------------------------------Yes 925 1451 161 Allow Creation of Missing Sections---------------------------No 925 1451 162 Allow Insertion of Energy Points-----------------------------No 925 1451 163 Create Uniform Energy Grid-----------------------------------No 925 1451 164 Delete Section if Cross Section =0 at All Energies-----------Yes 925 1451 165 ***************** Program GROUPIE (VERSION 2002-1) ************** 925 1451 166 Unshielded Group Averages Using 640 Groups 925 1451 167 Weighting Spectrum: Flat (Constant) Spectrum 925 1451 168 1 451 172 1 925 1451 169 2 151 4 1 925 1451 170 3 16 34 1 925 1451 171 33 16 71 1 925 1451 172 925 1 099999 925 0 0 0 9.01900E+3 1.88352E+1 0 0 1 0 925 2151 1 9.019000+3 1.000000+0 0 0 1 0 925 2151 2 1.000000-5 2.000000+7 0 0 0 0 925 2151 3 5.000000-1 5.360000-1 0 0 0 0 925 2151 4 925 2 099999 925 0 0 0 9.01900E+3 1.88352E+1 0 0 0 0 925 3 16 1 -1.04322E+7-1.04322E+7 0 0 1 92 925 3 16 2 92 1 925 3 16 3 10900000.0 2.02752E-6 11000000.0 5.63229E-5 11100000.0 .000137655 925 3 16 4 11200000.0 .000292275 11300000.0 .000548721 11400000.0 .000917543 925 3 16 5 11500000.0 .001402145 11600000.0 .002002095 11700000.0 .002714490 925 3 16 6 11800000.0 .003534705 11900000.0 .004456885 12000000.0 .005474310 925 3 16 7 12100000.0 .006579685 12200000.0 .007765400 12300000.0 .009023740 925 3 16 8 12400000.0 .010347050 12500000.0 .011727850 12600000.0 .013159000 925 3 16 9 12700000.0 .014633700 12800000.0 .016152650 12900000.0 .017695750 925 3 16 10 13000000.0 .019265950 13100000.0 .020863250 13200000.0 .022460550 925 3 16 11 13300000.0 .024071763 13400000.0 .025696888 13500000.0 .027322013 925 3 16 12 13600000.0 .028947138 13700000.0 .030572263 13800000.0 .032197388 925 3 16 13 13900000.0 .033822513 14000000.0 .035447638 14100000.0 .037049625 925 3 16 14 14200000.0 .038628475 14300000.0 .040207325 14400000.0 .041786175 925 3 16 15 14500000.0 .043331888 14600000.0 .044844463 14700000.0 .046357038 925 3 16 16 14800000.0 .047869613 14900000.0 .049339675 15000000.0 .050767225 925 3 16 17 15100000.0 .052194775 15200000.0 .053622325 15300000.0 .054999450 925 3 16 18 15400000.0 .056326150 15500000.0 .057652850 15600000.0 .058979550 925 3 16 19 15700000.0 .060248850 15800000.0 .061460750 15900000.0 .062672650 925 3 16 20 16000000.0 .063884550 16100000.0 .065033000 16200000.0 .066118000 925 3 16 21 16300000.0 .067203000 16400000.0 .068288000 16500000.0 .069304550 925 3 16 22 16600000.0 .070252650 16700000.0 .071200750 16800000.0 .072148850 925 3 16 23 16900000.0 .073024838 17000000.0 .073828713 17100000.0 .074632588 925 3 16 24 17200000.0 .075436463 17300000.0 .076166188 17400000.0 .076821763 925 3 16 25 17500000.0 .077477338 17600000.0 .078132913 17700000.0 .078714000 925 3 16 26 17800000.0 .079220600 17900000.0 .079727200 18000000.0 .080233800 925 3 16 27 18100000.0 .080667413 18200000.0 .081028038 18300000.0 .081388663 925 3 16 28 18400000.0 .081749288 18500000.0 .082040025 18600000.0 .082260875 925 3 16 29 18700000.0 .082481725 18800000.0 .082702575 18900000.0 .082858125 925 3 16 30 19000000.0 .082948375 19100000.0 .083038625 19200000.0 .083128875 925 3 16 31 19300000.0 .083180900 19400000.0 .083152770 19500000.0 .083082710 925 3 16 32 19600000.0 .083012650 19700000.0 .082942590 19800000.0 .082872530 925 3 16 33 19900000.0 .082740370 20000000.0 0.0 925 3 16 34 925 3 099999 925 0 0 0 9.01900E+3 1.88352E+1 0 0 0 1 92533 16 1 0.000000+0 0.000000+0 0 16 0 1 92533 16 2 0.000000+0 0.000000+0 1 5 406 28 92533 16 3 1.000000-5 1.090000+7 1.200000+7 1.250000+7 1.300000+7 1.350000+7 92533 16 4 1.400000+7 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7 92533 16 5 1.700000+7 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7 92533 16 6 2.000000+7 2.100000+7 2.200000+7 2.300000+7 2.400000+7 2.500000+7 92533 16 7 2.700000+7 2.800000+7 2.900000+7 3.000000+7 0.000000+0 0.000000+0 92533 16 8 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 9 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 10 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 11 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 12 0.000000+0 7.844560-3 4.898350-3 3.027060-3 1.929170-3 1.321910-3 92533 16 13 9.926111-4 8.097050-4 6.990610-4 6.218640-4 5.596050-4 5.048120-4 92533 16 14 4.555230-4 4.121780-4 3.758470-4 3.473540-4 3.269110-4 3.140740-4 92533 16 15 3.073570-4 3.120960-4 3.231580-4 3.310920-4 3.298620-4 3.041000-4 92533 16 16 2.525070-4 2.039030-4 1.464150-4 3.648070-3 2.360540-3 1.449110-3 92533 16 17 9.104930-4 6.319380-4 5.059420-4 4.569550-4 4.388680-4 4.266530-4 92533 16 18 4.088340-4 3.819840-4 3.470900-4 3.071470-4 2.656870-4 2.259100-4 92533 16 19 1.902720-4 1.486420-4 1.141580-4 1.016320-4 1.039070-4 1.134800-4 92533 16 20 1.281520-4 1.350840-4 1.314670-4 1.212070-4 1.826270-3 1.354210-3 92533 16 21 9.782671-4 7.059900-4 5.267220-4 4.207220-4 3.665780-4 3.449020-4 92533 16 22 3.398810-4 3.397380-4 3.365240-4 3.256910-4 3.054490-4 2.760780-4 92533 16 23 2.392420-4 1.754770-4 8.900070-5 1.611170-5-3.205140-5-5.099350-5 92533 16 24 -2.365820-5 5.330250-5 1.291950-4 2.188860-4 1.233180-3 1.050650-3 92533 16 25 8.482810-4 6.625510-4 5.129570-4 4.047920-4 3.347390-4 2.952800-4 92533 16 26 2.776250-4 2.733860-4 2.755370-4 2.787900-4 2.796490-4 2.762050-4 92533 16 27 2.614270-4 2.288330-4 1.889520-4 1.513570-4 1.231830-4 1.085890-4 92533 16 28 1.236560-4 1.520640-4 1.922260-4 1.030240-3 9.309550-4 7.910340-4 92533 16 29 6.422140-4 5.056870-4 3.931520-4 3.093600-4 2.543630-4 2.252570-4 92533 16 30 2.174790-4 2.257800-4 2.449250-4 2.701550-4 3.105180-4 3.558030-4 92533 16 31 3.811660-4 3.836510-4 3.655150-4 3.091160-4 2.316670-4 1.739440-4 92533 16 32 1.144030-4 9.301140-4 8.611210-4 7.506000-4 6.229440-4 4.974770-4 92533 16 33 3.876710-4 3.015590-4 2.426370-4 2.107830-4 2.032840-4 2.157690-4 92533 16 34 2.430530-4 3.003160-4 3.817500-4 4.465680-4 4.803090-4 4.784630-4 92533 16 35 4.115300-4 2.889300-4 1.821310-4 6.207860-5 8.648120-4 8.135850-4 92533 16 36 7.261930-4 6.210140-4 5.137590-4 4.162000-4 3.360620-4 2.773020-4 92533 16 37 2.407400-4 2.248090-4 2.263440-4 2.532360-4 3.094430-4 3.658040-4 92533 16 38 4.035410-4 4.133410-4 3.692840-4 2.697090-4 1.753330-4 6.488820-5 92533 16 39 8.276580-4 7.994630-4 7.403910-4 6.622230-4 5.756870-4 4.895590-4 92533 16 40 4.102830-4 3.420170-4 2.868660-4 2.452630-4 2.075860-4 1.890180-4 92533 16 41 1.937990-4 2.070150-4 2.180840-4 2.167570-4 1.920930-4 1.606910-4 92533 16 42 1.194350-4 8.367870-4 8.381600-4 8.077220-4 7.513760-4 6.760250-4 92533 16 43 5.886680-4 4.958200-4 4.031020-4 3.150170-4 2.001340-4 8.278800-5 92533 16 44 1.074360-5-2.078540-5-2.009100-5 2.343720-5 9.478700-5 1.508320-4 92533 16 45 2.094530-4 9.030970-4 9.293760-4 9.163470-4 8.669560-4 7.869960-4 92533 16 46 6.839560-4 5.660230-4 4.412210-4 2.582200-4 4.586960-5-1.068070-4 92533 16 47 -1.912730-4-2.107930-4-1.358110-4 2.138250-5 1.612100-4 3.183170-4 92533 16 48 1.012600-3 1.049310-3 1.037800-3 9.812610-4 8.866920-4 7.633760-4 92533 16 49 6.215440-4 3.970180-4 1.170730-4-1.006010-4-2.340860-4-2.800390-4 92533 16 50 -1.974460-4 1.093280-5 2.077500-4 4.350440-4 1.136340-3 1.170610-3 92533 16 51 1.152160-3 1.086070-3 9.810220-4 8.476920-4 6.195350-4 3.158060-4 92533 16 52 6.329550-5-1.052330-4-1.794050-4-1.175480-4 9.273780-5 3.048660-4 92533 16 53 5.562250-4 1.254720-3 1.286290-3 1.267530-3 1.204830-3 1.107390-3 92533 16 54 9.184080-4 6.431870-4 3.946850-4 2.121830-4 1.124980-4 1.261560-4 92533 16 55 2.843660-4 4.638940-4 6.851270-4 1.376450-3 1.420770-3 1.422120-3 92533 16 56 1.386320-3 1.278440-3 1.085040-3 8.822720-4 7.106800-4 5.921990-4 92533 16 57 5.353610-4 5.914810-4 6.921020-4 8.298950-4 1.539830-3 1.622460-3 92533 16 58 1.669850-3 1.679580-3 1.616300-3 1.498950-3 1.363950-3 1.236560-3 92533 16 59 1.094900-3 1.009270-3 9.922760-4 1.001160-3 1.798240-3 1.944450-3 92533 16 60 2.099870-3 2.205700-3 2.207720-3 2.133310-3 2.009010-3 1.777510-3 92533 16 61 1.524740-3 1.362900-3 1.209860-3 2.198710-3 2.517890-3 2.820120-3 92533 16 62 2.967440-3 2.974120-3 2.866070-3 2.549010-3 2.119470-3 1.798830-3 92533 16 63 1.465550-3 3.093180-3 3.712880-3 4.106620-3 4.263970-3 4.206430-3 92533 16 64 3.790030-3 3.114020-3 2.560510-3 1.957740-3 4.741660-3 5.470710-3 92533 16 65 5.854090-3 5.903210-3 5.430360-3 4.514070-3 3.710880-3 2.809610-3 92533 16 66 6.497010-3 7.107000-3 7.299680-3 6.881850-3 5.882950-3 4.952680-3 92533 16 67 3.884000-3 7.920590-3 8.280630-3 8.031330-3 7.128890-3 6.218540-3 92533 16 68 5.143690-3 8.820440-3 8.840330-3 8.205440-3 7.459920-3 6.540140-3 92533 16 69 9.408330-3 9.443150-3 9.180490-3 8.759390-3 1.037760-2 1.080020-2 92533 16 70 1.110710-2 1.176100-2 1.264710-2 1.416170-2 92533 16 71 92533 099999 925 0 0 0 0 0 0 0 -1 0 0 0