IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 93237.0000 235.011000 0 1 34 109346 1451 1 0.0 1.00000000 0 0 0 69346 1451 2 1.00000000 60000000.0 0 0 10 20029346 1451 3 300.000000 0.0 1 0 328 69346 1451 4 93-Np-237 FEI/LANL EVAL-May96 K.Zolotarev et al.,P.Young et al.9346 1451 5 DIST-Feb2004 9346 1451 6 ----IRDF-2002 MATERIAL 9346 9346 1451 7 -----INCIDENT NEUTRON DATA 9346 1451 8 ------ENDF-6 FORMAT 9346 1451 9 ******************************************************************9346 1451 10 IAEA, July 2011 (A. Trkov) 9346 1451 11 The IRDF-2002 cross sections file was extended in energy from 9346 1451 12 20 to 60 MeV using the data from the TENDL-2010 library. 9346 1451 13 ******************************************************************9346 1451 14 ***************************************************************** 9346 1451 15 93-Np-237 FEI EVAL-May96 K.Zolotarev et al. 9346 1451 16 DIST-Sep03 9346 1451 17 ----BROND-3 MATERIAL 9346 Revision 2, Oct. 2003 9346 1451 18 ***************************************************************** 9346 1451 19 ------Russian Reactor Dosimetry File RRDF-2002 9346 1451 20 ***************************************************************** 9346 1451 21 Authors of evaluation: K.I.Zolotarev, S.A.Badikov, A.I.Blokhin, 9346 1451 22 A.V.Ignatyuk 9346 1451 23 ***************************************************************** 9346 1451 24 9346 1451 25 ----- MF=2 MT=151 ----- 9346 1451 26 9346 1451 27 RESONANCE PARAMETERS 9346 1451 28 -------------------- 9346 1451 29 Resolved Resonance Region : 1.0E-5 - 600 eV 9346 1451 30 Resolved MLBW resonance parameters up to 600 eV were based on 9346 1451 31 on data from ref. [1]. 9346 1451 32 A statistical method of the resonance analysis showed that 9346 1451 33 the missing of the resonances becomes essential above the energy 9346 1451 34 of 150 eV. However only weak resonances are missed with the neut- 9346 1451 35 ron widths less than the average width by the factor 5-10. 9346 1451 36 The resonances with widths close to average or above it were 9346 1451 37 identified without the noticeable missing up to the energy of 9346 1451 38 600 eV. So as these resonances give dominant contribution into 9346 1451 39 the neutron cross sections the resolved resonances region was ex- 9346 1451 40 panded up to 600 eV and average contribution of the missed weak 9346 1451 41 resonances was taken into account by addition of relevant cross 9346 1451 42 section background in the file MF=3. (For fission cross sections 9346 1451 43 this background is equal to zero). 9346 1451 44 9346 1451 45 Unresolved Resonance Region : 600 eV - 6 keV 9346 1451 46 For the optical-statistical calculation of the cross sections 9346 1451 47 in the unresolved resonance region were used the following para- 9346 1451 48 meters: 9346 1451 49 Average resonance spacing - D0 = 0.57+-0.03 eV 9346 1451 50 Neutron strengh function - S0 = (0.97+-0.07)*104 9346 1451 51 Average radiation width - Gg = 40.0+-1.2 meV 9346 1451 52 This values were obtained as a result of the analysis resolwed 9346 1451 53 MLBW resonance parameters taking into account the missed resonan- 9346 1451 54 ces correction. 9346 1451 55 Considerable attention was paid to the analysis of fission 9346 1451 56 widths and elimination of contradictions in the description of 9346 1451 57 intermediate structure of averaged fission cross sections for the 9346 1451 58 neutron energies above 100 eV. The new experimental data [2-4] on 9346 1451 59 fission cross sections were included in the analysis. They were 9346 1451 60 obtained by LANL and JAERI physicists on their neutron spectrome- 9346 1451 61 ter [2,3] and by Dubna-Obninsk collaboration on the pulsed reac- 9346 1451 62 tor of JINR [4]. 9346 1451 63 The resulting set of resonance parameters reproduces well the 9346 1451 64 observed intermediate structure of fission cross sections (100 eV-9346 1451 65 6 keV). Corresponding group fission cross sections are 30-50 % 9346 1451 66 lower than JENDL-3.2 evaluation [5] and approximately twice 9346 1451 67 higher than ENDF/B-VI ones [6]. Corrected fission widths of the 9346 1451 68 neutron resonances below 100 eV also result in fission cross sec- 9346 1451 69 tions which are lower than JENDL-3.2 values [5]. 9346 1451 70 Calculated from the adopted resonance parameters 2200 M/S 9346 1451 71 cross sections and resonance integrals are agree rather well with 9346 1451 72 the recommended evaluated experimental data [1] : 9346 1451 73 9346 1451 74 Value This evaluation Experimental data [1] 9346 1451 75 Total 190.23 barn 9346 1451 76 Elastic 14.17 barn 9346 1451 77 Fission 0.0215 barn 0.0215+-0.0024 barn 9346 1451 78 Capture 176.04 barn 175.9+-2.9 barn 9346 1451 79 Fission res. int. 6.930 barn 6.9+-1.0 barn 9346 1451 80 Capture res. int. 642.30 barn 640+-50 barn 9346 1451 81 9346 1451 82 ----- MF=3 MT= 18 ----- 9346 1451 83 9346 1451 84 FISSION CROSS SECTIONS 9346 1451 85 ---------------------- 9346 1451 86 Np-237 fission cross sections from 1.0E-5 eV to 6 keV are re- 9346 1451 87 constructed from evaluated MLBW resolved and unresolved resonance 9346 1451 88 parameters. 9346 1451 89 For the evaluation of the Np-237(n,f) cross sections in the 9346 1451 90 neutron energy region of 6 keV - 20 MeV available experimental 9346 1451 91 data [7- 46] were analyzed. During this procedure experimental 9346 1451 92 data if it was possible were corrected to the new recommended 9346 1451 93 cross section data for monitor reactions used in the measurements 9346 1451 94 and to the new recommended decay data. 9346 1451 95 The top priority was given to absolute measurements where no 9346 1451 96 reference cross sections were used to determine the neutron flux 9346 1451 97 and to time-of-flight experiments with simultaneous registration 9346 1451 98 of the fission and monitoring reaction events. 9346 1451 99 In ten experiments the Np-237(n,f) cross sections were measu- 9346 1451 100 red relatively to the fission of U-235. The use as the standard 9346 1451 101 of the U-235 fission cross section from ENDF/B-VI [47] instead 9346 1451 102 of the old one (ENDF/B-V) results in decrease of the Np-237(n,f) 9346 1451 103 cross sections in average by 2 % in 0.1 - 2.0 MeV range and by 9346 1451 104 1.5 % in 2.0 - 3.0 MeV range. 9346 1451 105 In the work of Kupriyanov et al. [20] the Np-237(n,f) cross 9346 1451 106 sections were measured against the fission cross sections of 9346 1451 107 Pu-239. At the present time there are no recommended Pu-239 cross 9346 1451 108 sections as a standard data. The data from two libraries were 9346 1451 109 used to get absolute values: JENDL-3.2 [48] and ENDF/B-VI [49]. 9346 1451 110 Below 1.6 MeV the results of Ref. [20] disagree with the integral 9346 1451 111 experiments no matter which data are used for Pu-239(n,f) . The 9346 1451 112 analysis of Ref. [20] data demonstrated that the good agreement 9346 1451 113 with the rest of data may be obtained for the energy region of 9346 1451 114 1.6-7.0 MeV if Pu-239(n,f) reaction cross section data are taken 9346 1451 115 from JENDL-3.2 library. 9346 1451 116 The ratio of Np-237 to U-235 fission cross sections measured 9346 1451 117 by Behrens et al. [23] in 0.11 - 18.89 MeV energy range was multi-9346 1451 118 plied by factor of 1.051. This normalization factor was obtained 9346 1451 119 from the values of the functional / in 9346 1451 120 the 1 - 5 MeV energy range evaluated before. There is a lot of 9346 1451 121 experimental data which are in good agreement in this interval. 9346 1451 122 The ratio of the Np-237(n,f) evaluated averaged cross section for 9346 1451 123 the neutron spectrum of Cf-252 spontaneous fission, known from 9346 1451 124 many works, to the averaged data of Behrens et al. [23] is equal 9346 1451 125 to 1.055 that confirms our renormalization of these data. 9346 1451 126 The analysis of experimental data on the ratio of Np-237 and 9346 1451 127 U-235 fission cross sections indicates that the relative energy 9346 1451 128 trends of / measured by Terayama et al.9346 1451 129 [36] in the energy range of 4.19 - 6.99 MeV and by Goverdovskiy 9346 1451 130 et al. [32] in the 5.66 - 10.06 MeV energy range coincides with 9346 1451 131 the results of other authors. To make them agree in absolute 9346 1451 132 values Terayama et al. and Goverdovskiy et al. results were multi-9346 1451 133 plied by 0.96 and 1.079, respectively. The data on the Np-237 9346 1451 134 fission cross sections obtained by Terayama et al. on T(p,n)He-3 9346 1451 135 neutron source for the 0.70 - 2.99 MeV energy range are in good 9346 1451 136 agreement with the results of Refs. [38-40]. So they were correc- 9346 1451 137 ted only according to the new data on the monitoring reaction 9346 1451 138 U-235(n,f) [46]. 9346 1451 139 Experimental data of Meadows et al. [26] as well as that of 9346 1451 140 Kupriyanov et al. [20] are systematically too low below 1 MeV 9346 1451 141 that contradicts to the evaluated integral experiments 9346 1451 142 available. Above 1 MeV Meadows et al. [26] data well agree with 9346 1451 143 the results of other authors so they were included in the final 9346 1451 144 evaluation only above this energy. Data of Kupriyanov et al. [20] 9346 1451 145 were taken into account in the evaluation above 1.6 MeV. 9346 1451 146 Statistical analysis of the input experimental cross section 9346 1451 147 data for Np-237(n,f) reaction in 0.1-20 MeV neutron energy range 9346 1451 148 was carried out by means of PADE-2 code [50]. Rational function 9346 1451 149 was used as the model function [51]. 9346 1451 150 Averaged cross sections for U-235 thermal fission [52] and 9346 1451 151 Cf-252 spontaneous fission neutron spectra [53] calculated from 9346 1451 152 the evaluated Np-237(n,f) excitation function are the following: 9346 1451 153 9346 1451 154 ---------------------------------------------------------------- 9346 1451 155 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 9346 1451 156 ---------------------------------------------------------------- 9346 1451 157 U-235 neutron fission I 1356.2 I 1353.0 +- 24.0 [54] 9346 1451 158 I I 1350.0 +- 24.0 [55] 9346 1451 159 ---------------------------------------------------------------- 9346 1451 160 CF-252 spont. fission I 1359.9 I 1361.0 +- 21.6 [55] 9346 1451 161 ---------------------------------------------------------------- 9346 1451 162 9346 1451 163 Evaluated Np-237 fission cross section is in a good agreement 9346 1451 164 with the integral experiment data both for U-235 thermal fission 9346 1451 165 neutron spectrum and for Cf-252 spontaneous fission neutron spec- 9346 1451 166 trum. 9346 1451 167 The evaluated Np-237(n,f) cross section agrees within the ac- 9346 1451 168 curacy with integral experimental data for SIGNA-SIGMA field. 9346 1451 169 The Np-237 fission cross sections measured in CFRMF facility 9346 1451 170 are lower than calculated ones for any fission cross section eva- 9346 1451 171 luation. This apparently indicates the necessity of more detailed 9346 1451 172 and careful analysis of the CFRMF experimental data accuracy. 9346 1451 173 9346 1451 174 ----- MF=33 MT= 18----- 9346 1451 175 Uncertainties in the evaluated excitation function for the 9346 1451 176 Np-237(n,f) reaction are given in the two independent matrixes. 9346 1451 177 In the energy range 1.000E-05 eV - 0.1 MeV uncertainties are 9346 1451 178 given in the form of diagonal matrix of uncertainties for 6-th 9346 1451 179 neutron energy intervals (LB=1) 9346 1451 180 In the energy range 0.1 - 20 MeV uncertainties are presented 9346 1451 181 in the form of relative covariance matrix for the 48 -neutron 9346 1451 182 energy groups (LB=5). Eigenvalues of this 6-th digits relative 9346 1451 183 covariance matrix are the following: 9346 1451 184 9346 1451 185 1.49939E-07 1.52531E-07 1.53109E-07 1.53318E-07 9346 1451 186 1.54049E-07 1.55336E-07 1.56641E-07 1.58051E-07 9346 1451 187 1.58347E-07 1.60763E-07 1.63743E-07 1.64776E-07 9346 1451 188 1.67513E-07 1.69820E-07 1.73330E-07 1.75751E-07 9346 1451 189 1.77557E-07 2.05370E-07 2.66364E-07 2.70615E-07 9346 1451 190 2.75409E-07 2.80956E-07 2.93138E-07 3.15582E-07 9346 1451 191 3.35128E-07 4.86134E-07 7.89097E-07 3.07453E-06 9346 1451 192 1.65989E-05 9.67332E-05 1.24983E-04 1.51845E-04 9346 1451 193 4.05040E-04 4.14092E-04 5.11273E-04 5.63190E-04 9346 1451 194 7.24776E-04 8.29295E-04 9.68770E-04 9.77438E-04 9346 1451 195 1.07709E-03 1.13969E-03 1.57856E-03 1.84372E-03 9346 1451 196 2.04068E-03 2.65362E-03 3.89983E-03 1.60049E-02 9346 1451 197 9346 1451 198 References: 9346 1451 199 1. S.F.Mughabghab Neutron Cross Sections. N.Y.-London, Academic 9346 1451 200 Press, 1984, v.1, part B. 9346 1451 201 2. J.Kimura Nucl. Sci. Techn., v. 30, p.863, 1993 9346 1451 202 3. A.D.Carlson et al. Proc. of an Int. Conf. on Nuclear Data for 9346 1451 203 Science and Technology, Gatlinburg, Tennessee, USA, 9-13 May 9346 1451 204 1994, Ed. J.Dickens, ANS, Oak Ridge, 1994, v.1, p.40 9346 1451 205 4. A.A.Goverdovskiy et al. Jadernaja Fizika (Rus.), v.58, p.27, 9346 1451 206 January 1995 9346 1451 207 5. Y.Kikuchi Proc. of an Int. Conf. on Nuclear Data for Science 9346 1451 208 and Technology, Gatlinburg, Tennessee, USA, 9-13 May 1994, 9346 1451 209 Ed. J.Dickens, ANS, Oak Ridge, 1994, v.2, p.692 9346 1451 210 6. P.Young, E.Arthur, F.Mann ENDF/B-VI library, MAT 9346, 1990 9346 1451 211 7. E.D.Klema Phys. Rev., v.72, p.88, July 1947 9346 1451 212 8. R.L.Henkel Report LA-2114, 1957 9346 1451 213 R.L.Henkel Report LA-2122, June 1957 9346 1451 214 9. A.N.Protopopov et al. Atomnaja Energija (Sov.),v.4,p.190,1958 9346 1451 215 10. H.W.Schmitt, R.B.Murrey Phys. Rev., v.116, p.1575, 1959 9346 1451 216 10. R.B.Murrey, H.W.Schmitt Phys. Rev., v.115, p.1707, 1959 9346 1451 217 11. B.M.Gokhberg et al. Doklady Akademii Nauk SSSR, v.128,(6), 9346 1451 218 p.1157, 1959 9346 1451 219 12. V.M.Pankratov et al. Atomnaya Energiya, v.9, p.399, 1960 ??? 9346 1451 220 13. V.M.Pankratov Atomnaja Energiya (Sov.), v.14, p.177, 1963 9346 1451 221 14. J.A.Grundl Nucl. Sci. Eng., v.30, p.39, October 1967 9346 1451 222 15. P.H.White, G.P.Warner J. of Nucl. Energy, v.21, p.671, 1967 9346 1451 223 16. W.E.Stein, R.K.Smith, H.L.Smith Proceedings Conf. Neutron 9346 1451 224 Cross Sections and Technology, Washington, D.C., March 4-7, 9346 1451 225 1968, NBS Special Publication 299 , p.627 , U.S. National 9346 1451 226 Bureau of Standards, 1968 9346 1451 227 17. R.H.Iyer, R.Sampathkumar Proc. of 12th Symp. on Nuclear Phys. 9346 1451 228 and Solid State Phys., Roorkee, India, 28-31 December 1969, 9346 1451 229 v.2, p.289 ; 9346 1451 230 R.H.Iyer, R.Sampathkumar Prog. Report BARC/I-79, p.55, 1970 9346 1451 231 18. W.K.Brown et al. Nucl. Phys., vA156, p.609, November 1970 9346 1451 232 19. R.J.Jiacoletti, W.K.Brown, H.G.Olson. Nucl. Sci. Eng., v.48, 9346 1451 233 p.412, August 1972 9346 1451 234 20. V.M.Kupriyanov et al. Atomnaya Energiya, v.45, p.440, 1978 9346 1451 235 21. D.J.Grady et al. Proc. of an Int. Conf. on Nuclear Cross 9346 1451 236 Sections for Technology, Knoxville, Tennessee, 22-26 October 9346 1451 237 1979, NBS Special Publ.594, p.976, September 1980 9346 1451 238 22. R.Arlt et al. Report ZFK-410, p.122, January 1980 ; 9346 1451 239 R.Arlt et al. Kernenergie, v.24, p.48, February 1981 9346 1451 240 23. J.W.Behrens, J.C.Browne, J.C.Malden Nucl. Sci. Eng., v.80, 9346 1451 241 p.393, 1982 9346 1451 242 24. M.Cance, G.Grenier Proc of an Int. Conf. on Nuclear Data 9346 1451 243 for Science and Technology, Antwerp, 6-10 September 1982, 9346 1451 244 Dr. Reidel Publishing Company, 1983, p.51 9346 1451 245 25. M.Varnagy, S.Juhasz, J.Csikai Nucl. Instr. Meth., v.196, 9346 1451 246 p.465, May 1982 9346 1451 247 26. J.W.Meadows Nucl. Sci. Eng., v.85, p.271, November 1983 9346 1451 248 27. I.D.Alkhazov, E.A.Ganza, L.V.Drapchinskij et al. Proceedings 9346 1451 249 of the 3-d All-union Conference on the Neutron Radiation 9346 1451 250 Metrology at Reactors and Accelerators, v.2, p.201, Moscow, 9346 1451 251 CNIIATOMINFORM, 1983 9346 1451 252 28. K.R.Zasadny et al. J. Trans. Amer. Nucl. Soc., v.47, p.425, 9346 1451 253 November 1984 9346 1451 254 29. Wu Jingxia et al. Chinese J. of Nuclear Physics, v.6, p.369, 9346 1451 255 November 1984 9346 1451 256 30. I.Garlea et al. Revue Roumaine de Physique, v.29, p.421, 1984 9346 1451 257 31. A.A.Goverdovski et al. Preprint FEI-1552, Obninsk, 1984 9346 1451 258 32. A.A.Goverdovskij et al. VANT, Serija: Yadernye Konstanty, 9346 1451 259 issue 3(57), p.13, September 1984 9346 1451 260 33. K.Kanda et al. Report JAERI-M-85-035, p.220, 1985 9346 1451 261 34. R.Arlt et al. Isotopenpraxis, v.21, p.344, 1985 9346 1451 262 35. A.A.Goverdovskij et al. Atomnaja Energija (Sov.), v.58, no.2,9346 1451 263 p.137, February 1985 9346 1451 264 36. H.Terayama et al. Progress Report NETU-47, 1986 ; 9346 1451 265 H.Terayama et al. Progress Report NEANDC(J)-122, Sep. 1986 9346 1451 266 37. I.D.Alkhazov et al. VANT, Serija: Yadernye Konstanty, v.4, 9346 1451 267 p.19, December 1986 9346 1451 268 38. V.A.Kalinin et al. VANT, Serija: Yadernye Konstanty, v.4, 9346 1451 269 p.3, December 1987 9346 1451 270 39. P.W.Lisowski et al. Proc. of an Int. Conf. on Nuclear Data 9346 1451 271 for Science and Technology, Mito, Japan, 30 May-3 June 1988, 9346 1451 272 pp. 97-99 9346 1451 273 40. J.W.Meadows Annals of Nucl. Energy, v.15, p.421, August 1988 9346 1451 274 41. J.W.Meadows, D.L.Smith, L.P.Geraldo Annals of Nucl. Energy, 9346 1451 275 v.16, p.471, September 1989 9346 1451 276 36. L.Desdin, S.Szegedi, J.Csikai Acta Physica Hungaria, v.65, 9346 1451 277 p.271, 1989 9346 1451 278 43. P.W.Lisowski et al. Proc. of the Conference on Fifty Years 9346 1451 279 with Nuclear Fission, NIST, Gaithersburg, MD, 1989, p.443 9346 1451 280 44. K.Merla et al. Proc. of an Int. Conf. on Nuclear Data for 9346 1451 281 Science and Technology, Julich, FRG, 13-17 May 1991. Springer 9346 1451 282 Verlag, Berlin - Heidelberg, 1992, p.510-513 9346 1451 283 45. A.D.Carlson et al. Proc. of an Int. Conf. on Nuclear Data for 9346 1451 284 Science and Technology, Gatlinburg, Tennessee, USA, May 9-13, 9346 1451 285 1994, Vol.1, pp. 40-42 9346 1451 286 46. T.Iwasaki et al. Nucl. Sci. Technology, v.36, p.127, 1999 9346 1451 287 47. L.Weston et al. ORNL,LANL eval. April 1989, ENDF/B-VI Library 9346 1451 288 MAT=9228; 9346 1451 289 H.Conde ed. Nuclear Data Standards for Nuclear Measurements, 9346 1451 290 Report NEANDC-311 U, p.51-58, OECD, Paris, 1992. 9346 1451 291 48. M.Kawai et al. eval. NAIG, JENDL-3.2 library, MAT=9437, 9346 1451 292 Rev. 2, February 1993 9346 1451 293 49. P.Young et al. eval. ORNL, LANL , ENDF/B-VI library, MAT=9437,9346 1451 294 Rev.1, January 1993 9346 1451 295 50. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 9346 1451 296 51. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 9346 1451 297 st's Meeting on Evaluation and Processing of Covariance Data, 9346 1451 298 Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105 9346 1451 299 52. L.W.Weston et al. Evaluated Neutron Data for Uranium-235, 9346 1451 300 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 9346 1451 301 53. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 9346 1451 302 54. W.Mannhart Prog. Report INDC(Ger)-045, pp.40-43, June 1999 9346 1451 303 55. W.Mannhart Validation of Differential Cross Sections with 9346 1451 304 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 9346 1451 305 September 2002 9346 1451 306 ******************************************************************9346 1451 307 ----- MF=3 MT= 1 ----- 9346 1451 308 ----- MF=3 MT= 2 ----- 9346 1451 309 93-NP-237 LANL EVAL-APR90 P.YOUNG, E.ARTHUR, F.MANN 9346 1451 310 DIST-SEP91 REV1-JUL91 19910806 9346 1451 311 ----ENDF/B-VI MATERIAL 9346 REVISION 1 9346 1451 312 MT=1 Neutron Total Cross Section. Derrien evaluation (De80, 9346 1451 313 De89) used from 1.0E-5 eV to 0.008 MeV. Above 0.008 MeV,9346 1451 314 coupled channel optical model calculations (ECIS code) 9346 1451 315 with modified Lagrange (Ha80) potential used as prior 9346 1451 316 in a covariance analysis of measurement by Lisowski et 9346 1451 317 al. from 3 to 20 MeV (Li90). 9346 1451 318 MT=2 All Energies, based on subtraction of MT=4,16,17,18,37, 9346 1451 319 and 102 from MT=1. 9346 1451 320 ******************************************************************9346 1451 321 The cross sections for total and elastic were modified between 9346 1451 322 6 and 10 Kev for continuity with the data of Zolatarev file 18. 9346 1451 323 The number of interpolation schemes is set to 1. 9346 1451 324 9346 1451 325 ******************************************************************9346 1451 326 ***************** Program LINEAR (VERSION 2012-1) ***************9346 1451 327 For All Data Greater than 1.0000D-10 barns in Absolute Value 9346 1451 328 Data Linearized to Within an Accuracy of .100000000 per-cent 9346 1451 329 ***************** Program GROUPIE (VERSION 2012-1) **************9346 1451 330 Unshielded Group Averages Using 640 Groups 9346 1451 331 Weighting Spectrum: Flat (Constant) Spectrum 9346 1451 332 1 451 332 19346 1451 333 2 151 4 19346 1451 334 3 1 7616 19346 1451 335 3 2 3595 19346 1451 336 3 18 10642 19346 1451 337 33 18 229 19346 1451 338 9346 1 0 339 9346 0 0 340 93237.0000 235.011000 0 0 1 09346 2151 341 9.323700+4 1.000000+0 0 0 1 09346 2151 342 1.000000-5 6.000000+2 0 0 0 09346 2151 343 2.500000+0 9.540000-1 0 0 0 09346 2151 344 9346 2 0 345 9346 0 0 346 93237.0100 235.011000 0 0 0 09346 3 1 347 0.0 0.0 0 0 1 6419346 3 1 348 641 1 9346 3 1 349 1.00000E-4 2867.47860 1.05000E-4 2800.80690 1.10000E-4 2737.471249346 3 1 350 1.15000E-4 2679.11413 1.20000E-4 2610.89121 1.27500E-4 2535.200519346 3 1 351 1.35000E-4 2466.05929 1.42500E-4 2402.52201 1.50000E-4 2333.757879346 3 1 352 1.60000E-4 2262.12518 1.70000E-4 2196.95615 1.80000E-4 2137.143249346 3 1 353 1.90000E-4 2081.49675 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