ENTRY 10091 19991013 13501009100000001 SUBENT 10091001 19991013 13501009100100001 BIB 9 18 1009100100002 INSTITUTE (1USATNC) 1009100100003 REFERENCE (R,DASA-2333,196907) 1009100100004 (J,BAP,15,1667,197012) 1009100100005 AUTHOR (W.E.Tucker,P.S.Buchanan,T.C.Martin,D.O.Nellis, 1009100100006 G.H.Williams) 1009100100007 TITLE Neutron induced gamma-ray production cross sections 1009100100008 for silicon and tungsten. 1009100100009 SAMPLE Right-circular cylindrical scattering sample of 1009100100010 natural silicon 1.57 cm diameter and 3.97 cm long. 1009100100011 METHOD (TOF) Time-of-flight method 1009100100012 MONITOR Flux monitored with proton recoil detector. 1009100100013 STATUS (PRELM) Preliminary 1009100100014 Data taken from tables in report. 1009100100015 HISTORY (19730130C) 1009100100016 (19750905A) REFERENCE added 1009100100017 (19811216A) Converted to REACTION formalism 1009100100018 (19850115A) BIB orrections. 1009100100019 (19991013A) Converted to new data formalism. 1009100100020 ENDBIB 18 0 1009100100021 NOCOMMON 0 0 1009100100022 ENDSUBENT 21 0 1009100199999 SUBENT 10091002 20081020 13501009100200001 BIB 7 17 1009100200002 REACTION (14-SI-0(N,X)0-G-0,PAR,DA) 1009100200003 FACILITY (VDG,1USATNC) 3.2 MeV Van de Graaff accelerator 1009100200004 INC-SOURCE (D-D) 1009100200005 DETECTOR (GELI) G(e)L(i) detector 1009100200006 (NAICR) NaI(Tl) scintillation detector 1009100200007 FLAG (1.) Average gamma ray energies for a group of 1009100200008 unresolved lines 1009100200009 (2.) 1.779 MeV gamma may contain minor contributions 1009100200010 from unresolved 1.763 and 1.796 MeV gammas. No 1009100200011 real evidence of these gamma rays could be seen. 1009100200012 ERR-ANALYS (DATA-ERR) Errors given include statistical errors and 1009100200013 possible stripping errors along with uncertianty in 1009100200014 detector efficiency, incident neutron flux, geometry 1009100200015 factors, incident neutron anisotropy, neutron 1009100200016 attenuation in scatterer, and gamma-ray absorption 1009100200017 in scatterer. 1009100200018 HISTORY (20081020A) Bookeeping corrected. 1009100200019 ENDBIB 17 0 1009100200020 COMMON 3 3 1009100200021 EN EN-ERR ANG 1009100200022 MEV MEV ADEG 1009100200023 5.0 0.1 55. 1009100200024 ENDCOMMON 3 0 1009100200025 DATA 4 8 1009100200026 E DATA DATA-ERR FLAG 1009100200027 MEV MB/SR MB/SR NO-DIM 1009100200028 0.759 0.3 0.1 1009100200029 1.037 0.6 0.2 1009100200030 1.27 1.5 0.2 1. 1009100200031 1.779 47.0 5.6 2. 1009100200032 2.032 1.0 0.2 1009100200033 2.232 1.3 0.2 1009100200034 2.427 0.5 0.1 1009100200035 2.838 1.0 0.2 1009100200036 ENDDATA 10 0 1009100200037 ENDSUBENT 36 0 1009100299999 SUBENT 10091003 19991013 00001009100300001 BIB 5 17 1009100300002 REACTION (14-SI-0(N,X)0-G-0,PAR,DA) 1009100300003 Total unresolved continuum cross section 1009100300004 FACILITY (VDGT,1USALAS) Tandem accelerator facility of Los 1009100300005 Alamos Scientific Laboratory 1009100300006 DETECTOR (GELI) G(e)L(i) detector for 390 and 399 keV gammas. 1009100300007 (NAICR) NaI(Tl) scintillation detector for gamma 1009100300008 energy > 550 keV. 1009100300009 METHOD The difference between the total NaI(Tl) cross section 1009100300010 plus the 0.390 and 0.399 MeV lines and the sum of the 1009100300011 discrete lines was designated the total unresolved 1009100300012 continuum cross section. 1009100300013 ERR-ANALYS (DATA-ERR) Errors given include statistical errors and 1009100300014 possible stripping errors along with uncertianty in 1009100300015 detector efficiency, incident neutron flux, geometry 1009100300016 factors, incident neutron anisotropy, neutron 1009100300017 attenuation in scatterer, and gamma-ray absorption 1009100300018 in scatterer. 1009100300019 ENDBIB 17 0 1009100300020 COMMON 2 3 1009100300021 E-MIN ANG 1009100300022 MEV ADEG 1009100300023 0.55 55. 1009100300024 ENDCOMMON 3 0 1009100300025 DATA 4 4 1009100300026 EN EN-ERR DATA DATA-ERR 1009100300027 MEV MEV MB/SR MB/SR 1009100300028 8.0 0.15 10.4 1.6 1009100300029 9.0 0.15 20.8 3.1 1009100300030 10.0 0.15 28.4 4.3 1009100300031 11.0 0.15 45.4 6.8 1009100300032 ENDDATA 6 0 1009100300033 ENDSUBENT 32 0 1009100399999 SUBENT 10091004 19991013 00001009100400001 BIB 6 13 1009100400002 REACTION ((14-SI-0(N,X)0-G-0,PAR,DA)// 1009100400003 (14-SI-0(N,X)0-G-0,PAR,DA)) 1009100400004 FACILITY (VDG,1USATNC) 3.2 MeV Van de Graaff accelerator 1009100400005 INC-SOURCE (D-D) For 5.0 MeV neutrons 1009100400006 DETECTOR (GELI) G(e)L(i) detector 1009100400007 (NAICR) NaI(Tl) scintillation detector 1009100400008 ERR-ANALYS (DATA-ERR) Errors given include statistical errors and 1009100400009 possible stripping errors along with uncertianty in 1009100400010 detector efficiency, incident neutron flux, geometry 1009100400011 factors, incident neutron anisotropy, neutron 1009100400012 attenuation in scatterer, and gamma-ray absorption 1009100400013 in scatterer. 1009100400014 HISTORY (19991013A) REACTION updated. 1009100400015 ENDBIB 13 0 1009100400016 COMMON 3 3 1009100400017 EN E ANG-DN 1009100400018 MEV MEV ADEG 1009100400019 5. 1.779 90. 1009100400020 ENDCOMMON 3 0 1009100400021 DATA 3 5 1009100400022 ANG-NM DATA DATA-ERR 1009100400023 ADEG NO-DIM NO-DIM 1009100400024 30. 1.359 0.094 1009100400025 55. 1.199 0.084 1009100400026 70. 1.119 0.078 1009100400027 90. 1.000 0.050 1009100400028 125. 1.177 0.082 1009100400029 ENDDATA 7 0 1009100400030 ENDSUBENT 29 0 1009100499999 SUBENT 10091005 19991013 00001009100500001 BIB 6 15 1009100500002 REACTION ((14-SI-0(N,X)0-G-0,PAR,DA)// 1009100500003 (14-SI-0(N,X)0-G-0,PAR,DA)) 1009100500004 FACILITY (VDGT,1USALAS) Tandem accelerator facility of Los 1009100500005 Alamos Scientific Laboratory 1009100500006 INC-SOURCE (P-T) For 8.0, 9.0, 10.0 and 11.0 MeV neutrons 1009100500007 DETECTOR (GELI) G(e)L(i) detector 1009100500008 (NAICR) NaI(Tl) scintillation detector 1009100500009 FLAG (1.) Gamma-ray energies are average values for a group 1009100500010 of unresolved lines 1009100500011 ERR-ANALYS (DATA-ERR) Errors given include statistical errors and 1009100500012 possible stripping errors along with uncertianty in 1009100500013 detector efficiency, incident neutron flux, geometry 1009100500014 factors, incident neutron anisotropy, neutron 1009100500015 attenuation in scatterer, and gamma-ray absorption 1009100500016 in scatterer. 1009100500017 ENDBIB 15 0 1009100500018 COMMON 3 3 1009100500019 EN ANG-NM ANG-DN 1009100500020 MEV ADEG ADEG 1009100500021 8.0 55. 90. 1009100500022 ENDCOMMON 3 0 1009100500023 DATA 4 7 1009100500024 E DATA DATA-ERR FLAG 1009100500025 MEV NO-DIM NO-DIM NO-DIM 1009100500026 1.779 1.420 0.114 1009100500027 2.838 1.523 0.137 1009100500028 3.196 1.103 0.143 1009100500029 4.497 1.000 0.137 1009100500030 5.10 1.283 0.110 1. 1009100500031 6.878 1.400 0.179 1009100500032 7.40 1.333 0.223 1009100500033 ENDDATA 9 0 1009100500034 ENDSUBENT 33 0 1009100599999 SUBENT 10091006 19991013 00001009100600001 BIB 6 10 1009100600002 REACTION (74-W-0(N,X)0-G-0,PAR,DA) 1009100600003 FACILITY (VDGT,1USALAS) Tandem accelerator facility of Los 1009100600004 Alamos Scientific Laboratory 1009100600005 INC-SOURCE (P-T) 1009100600006 DETECTOR (GELI) G(e)L(i) detector 1009100600007 FLAG (1.) Isotope identification undetermined 1009100600008 (2.) Assigned to 182W 1009100600009 (3.) Assigned to 184W 1009100600010 (4.) Assigned to 186W 1009100600011 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1009100600012 ENDBIB 10 0 1009100600013 COMMON 3 3 1009100600014 EN ANG DATA-ERR 1009100600015 MEV ADEG PER-CENT 1009100600016 8. 55. 20. 1009100600017 ENDCOMMON 3 0 1009100600018 DATA 4 12 1009100600019 E E DATA FLAG 1009100600020 MEV MEV MB/SR NO-DIM 1009100600021 0.384 7.6 3. 1009100600022 0.412 5.5 4. 1009100600023 0.462 3.1 1. 1009100600024 0.608 12. 4. 1009100600025 0.730 19.0 4. 1009100600026 0.771 6.5 3. 1009100600027 0.793 9.6 3. 1009100600028 0.895 0.904 19.0 3. 1009100600029 0.928 2.9 2. 1009100600030 0.997 4.5 1. 1009100600031 1.122 14. 2. 1009100600032 1.222 1.237 11. 1. 1009100600033 ENDDATA 14 0 1009100600034 ENDSUBENT 33 0 1009100699999 SUBENT 10091007 19991013 00001009100700001 BIB 2 2 1009100700002 REACTION (74-W-0(N,X)0-G-0,PAR,DA) 1009100700003 HISTORY (19850115A) MOVED TO AN 13006. 1009100700004 ENDBIB 2 0 1009100700005 NOCOMMON 0 0 1009100700006 NODATA 0 0 1009100700007 ENDSUBENT 6 0 1009100799999 SUBENT 10091008 19811216 00001009100800001 BIB 5 7 1009100800002 REACTION (74-W-0(N,X)0-G-0,PAR,DA,,AV) 1009100800003 Average of two 90. degree and one 125. degree run. 1009100800004 FACILITY (VDGT,1USALAS) Tandem accelerator facility of Los 1009100800005 Alamos Scientific Laboratory 1009100800006 INC-SOURCE (P-T) 1009100800007 DETECTOR (NAICR) NaI(Tl) scintillation detector 1009100800008 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1009100800009 ENDBIB 7 0 1009100800010 COMMON 3 3 1009100800011 EN ANG ANG 1009100800012 MEV ADEG ADEG 1009100800013 8.0 90. 125. 1009100800014 ENDCOMMON 3 0 1009100800015 DATA 4 13 1009100800016 E-MIN E-MAX DATA DATA-ERR 1009100800017 MEV MEV MB/SR MB/SR 1009100800018 0.75 1.00 124.7 18.7 1009100800019 1.00 1.25 89.1 13.4 1009100800020 1.25 1.50 71.5 10.7 1009100800021 1.50 1.75 50.7 7.6 1009100800022 1.75 2.00 43.5 6.5 1009100800023 2.0 2.5 82.9 12.4 1009100800024 2.5 3.0 62.0 11.2 1009100800025 3.0 3.5 38.6 6.9 1009100800026 3.5 4.0 28.1 5.1 1009100800027 4.0 4.5 17.9 3.2 1009100800028 4.5 5.0 9.6 2.4 1009100800029 5.0 5.5 5.5 1.9 1009100800030 5.5 6.0 3.6 1.3 1009100800031 ENDDATA 15 0 1009100800032 ENDSUBENT 31 0 1009100899999 SUBENT 10091009 19811216 00001009100900001 BIB 5 6 1009100900002 REACTION (74-W-0(N,X)0-G-0,PAR,DA) 1009100900003 FACILITY (VDGT,1USALAS) Tandem accelerator facility of Los 1009100900004 Alamos Scientific Laboratory 1009100900005 INC-SOURCE (P-T) 1009100900006 DETECTOR (NAICR) NaI(Tl) scintillation detector 1009100900007 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1009100900008 ENDBIB 6 0 1009100900009 COMMON 1 3 1009100900010 ANG 1009100900011 ADEG 1009100900012 125. 1009100900013 ENDCOMMON 3 0 1009100900014 DATA 5 42 1009100900015 EN E-MIN E-MAX DATA DATA-ERR 1009100900016 MEV MEV MEV MB/SR MB/SR 1009100900017 9.0 0.75 1.00 158.1 23.7 1009100900018 9.0 1.00 1.25 111.7 16.8 1009100900019 9.0 1.25 1.50 74.9 11.2 1009100900020 9.0 1.50 1.75 49.1 7.4 1009100900021 9.0 1.75 2.00 43.9 6.6 1009100900022 9.0 2.0 2.5 71.7 10.8 1009100900023 9.0 2.5 3.0 50.6 9.1 1009100900024 9.0 3.0 3.5 30.9 5.6 1009100900025 9.0 3.5 4.0 20.6 3.7 1009100900026 9.0 4.0 4.5 12.3 2.2 1009100900027 9.0 4.5 5.0 7.6 1.9 1009100900028 9.0 5.0 5.5 4.1 1.4 1009100900029 9.0 5.5 6.0 2.8 1.0 1009100900030 9.0 6.0 6.5 1.2 0.6 1009100900031 10. 0.75 1.0 201.7 30.3 1009100900032 10. 1.00 1.25 118.6 17.8 1009100900033 10. 1.25 1.50 79.9 12.0 1009100900034 10. 1.50 1.75 41.1 6.2 1009100900035 10. 1.75 2.00 34.0 5.1 1009100900036 10. 2.0 2.5 45.5 6.8 1009100900037 10. 2.5 3.0 29.5 5.3 1009100900038 10. 3.0 3.5 18.1 2.5 1009100900039 10. 3.5 4.0 12.5 1.9 1009100900040 10. 4.0 4.5 8.1 1.3 1009100900041 10. 4.5 5.0 5.2 1.1 1009100900042 10. 5.0 5.5 2.9 0.9 1009100900043 10. 5.5 6.0 2.6 0.9 1009100900044 10. 6.0 6.5 1.9 0.8 1009100900045 11. 0.75 1.0 238.8 35.8 1009100900046 11. 1.00 1.25 129.5 19.4 1009100900047 11. 1.25 1.50 71.8 10.8 1009100900048 11. 1.50 1.75 55.4 8.3 1009100900049 11. 1.75 2.00 32.9 4.9 1009100900050 11. 2.0 2.5 36.0 5.4 1009100900051 11. 2.5 3.0 16.9 2.8 1009100900052 11. 3.0 3.5 11.3 1.8 1009100900053 11. 3.5 4.0 7.3 1.2 1009100900054 11. 4.0 4.5 4.0 0.6 1009100900055 11. 4.5 5.0 2.5 0.7 1009100900056 11. 5.0 5.5 0.6 0.6 1009100900057 11. 5.5 6.0 0.6 0.4 1009100900058 11. 6.0 6.5 0.2 0.2 1009100900059 ENDDATA 44 0 1009100900060 ENDSUBENT 59 0 1009100999999 SUBENT 10091010 19991013 00001009101000001 BIB 6 22 1009101000002 REACTION (14-SI-0(N,X)0-G-0,PAR,DA) 1009101000003 FACILITY (VDGT,1USALAS) Tandem accelerator facility of Los 1009101000004 Alamos Scientific Laboratory 1009101000005 INC-SOURCE (P-T) 1009101000006 DETECTOR (GELI) G(e)L(i) detector 1009101000007 (NAICR) NaI(Tl) scintillation detector 1009101000008 FLAG (1.) Average gamma ray energies for a group of 1009101000009 unresolved lines 1009101000010 (2.) 1.779 MeV gamma may contain minor contributions 1009101000011 from unresolved 1.763 and 1.796 MeV gammas. No 1009101000012 real evidence of these gamma rays could be seen. 1009101000013 (3.) May contain a small contribution from the 1009101000014 unresolvable 1.602 MeV gamma ray. 1009101000015 (4.) Average gamma ray energies for a group of 1009101000016 unresolved lines. May contain a small contribution 1009101000017 from the unresolvable 1.602 MeV gamma ray. 1009101000018 ERR-ANALYS (DATA-ERR) Errors given include statistical errors and 1009101000019 possible stripping errors along with uncertianty in 1009101000020 detector efficiency, incident neutron flux, geometry 1009101000021 factors, incident neutron anisotropy, neutron 1009101000022 attenuation in scatterer, and gamma-ray absorption 1009101000023 in scatterer. 1009101000024 ENDBIB 22 0 1009101000025 COMMON 1 3 1009101000026 ANG 1009101000027 ADEG 1009101000028 55. 1009101000029 ENDCOMMON 3 0 1009101000030 DATA 7 122 1009101000031 EN EN-ERR E E DATA DATA-ERR 1009101000032 FLAG 1009101000033 MEV MEV MEV MEV MB/SR MB/SR 1009101000034 NO-DIM 1009101000035 8. 0.15 0.390 0.9 0.1 1009101000036 1009101000037 8. 0.15 0.399 0.7 0.1 1009101000038 1009101000039 8. 0.15 0.585 3.7 0.5 1009101000040 1009101000041 8. 0.15 0.942 2.0 0.4 1009101000042 1009101000043 8. 0.15 0.98 4.0 0.5 1009101000044 1. 1009101000045 8. 0.15 1.010 1.8 0.4 1009101000046 1009101000047 8. 0.15 1.113 1.1 0.3 1009101000048 1009101000049 8. 0.15 1.27 2.6 0.5 1009101000050 1. 1009101000051 8. 0.15 1.341 1.0 0.3 1009101000052 1009101000053 8. 0.15 1.53 3.2 1.4 1009101000054 1. 1009101000055 8. 0.15 1.59 2.3 0.5 1009101000056 4. 1009101000057 8. 0.15 1.614 3.9 0.6 1009101000058 3. 1009101000059 8. 0.15 1.633 1.1 0.3 1009101000060 1009101000061 8. 0.15 1.659 1.2 0.3 1009101000062 1009101000063 8. 0.15 1.779 60.4 7.2 1009101000064 2. 1009101000065 8. 0.15 1.809 0.6 0.2 1009101000066 1009101000067 8. 0.15 1.963 0.4 0.2 1009101000068 1009101000069 8. 0.15 2.032 2.1 0.4 1009101000070 1009101000071 8. 0.15 2.203 0.7 0.2 1009101000072 1009101000073 8. 0.15 2.232 2.3 0.4 1009101000074 1009101000075 8. 0.15 2.838 10.2 1.3 1009101000076 1009101000077 8. 0.15 3.196 3.2 0.5 1009101000078 1009101000079 8. 0.15 4.497 4.2 0.7 1009101000080 1009101000081 8. 0.15 4.911 2.0 0.7 1009101000082 1009101000083 8. 0.15 5.10 5.8 0.9 1009101000084 1. 1009101000085 8. 0.15 5.60 0.7 0.3 1009101000086 1. 1009101000087 8. 0.15 6.878 2.3 0.3 1009101000088 1009101000089 8. 0.15 7.40 1.3 0.2 1009101000090 1. 1009101000091 9.0 0.15 0.390 1.0 0.3 1009101000092 1009101000093 9.0 0.15 0.399 0.4 0.1 1009101000094 1009101000095 9.0 0.15 0.585 3.8 0.5 1009101000096 1009101000097 9.0 0.15 0.856 0.4 0.1 1009101000098 1009101000099 9.0 0.15 0.942 0.9 0.2 1009101000100 1009101000101 9.0 0.15 0.98 3.7 0.5 1009101000102 1. 1009101000103 9.0 0.15 1.010 1.0 0.2 1009101000104 1009101000105 9.0 0.15 1.113 0.6 0.2 1009101000106 1009101000107 9.0 0.15 1.27 1.8 0.3 1009101000108 1. 1009101000109 9.0 0.15 1.341 0.8 0.2 1009101000110 1009101000111 9.0 0.15 1.380 1.0 0.2 1009101000112 1009101000113 9.0 0.15 1.53 2.1 0.9 1009101000114 1. 1009101000115 9.0 0.15 1.59 3.0 0.4 1009101000116 4. 1009101000117 9.0 0.15 1.614 2.8 0.4 1009101000118 3. 1009101000119 9.0 0.15 1.633 1.1 0.2 1009101000120 1009101000121 9.0 0.15 1.659 1.0 0.2 1009101000122 1009101000123 9.0 0.15 1.779 39.9 4.8 1009101000124 2. 1009101000125 9.0 0.15 1.809 0.6 0.2 1009101000126 1009101000127 9.0 0.15 1.963 0.7 0.2 1009101000128 1009101000129 9.0 0.15 2.032 1.0 0.3 1009101000130 1009101000131 9.0 0.15 2.203 2.232 1.9 0.3 1009101000132 1009101000133 9.0 0.15 2.838 5.5 0.7 1009101000134 1009101000135 9.0 0.15 3.196 3.2 0.4 1009101000136 1009101000137 9.0 0.15 4.497 3.8 0.6 1009101000138 1009101000139 9.0 0.15 4.911 1.6 0.4 1009101000140 1009101000141 9.0 0.15 5.10 5.3 0.9 1009101000142 1. 1009101000143 9.0 0.15 5.60 1.4 0.3 1009101000144 1. 1009101000145 9.0 0.15 6.002 0.6 0.3 1009101000146 1009101000147 9.0 0.15 6.019 0.6 0.3 1009101000148 1009101000149 9.0 0.15 6.878 3.4 0.5 1009101000150 1009101000151 9.0 0.15 7.40 2.1 0.3 1009101000152 1. 1009101000153 9.0 0.15 7.935 1.0 0.2 1009101000154 1009101000155 10. 0.15 0.390 0.399 1.4 0.2 1009101000156 1009101000157 10. 0.15 0.585 3.9 0.5 1009101000158 1009101000159 10. 0.15 0.856 0.7 0.2 1009101000160 1009101000161 10. 0.15 0.942 1.2 0.2 1009101000162 1009101000163 10. 0.15 0.98 3.1 0.4 1009101000164 1. 1009101000165 10. 0.15 1.01 0.8 0.2 1009101000166 1009101000167 10. 0.15 1.113 0.4 0.2 1009101000168 1009101000169 10. 0.15 1.27 1.7 0.3 1009101000170 1. 1009101000171 10. 0.15 1.341 0.6 0.2 1009101000172 1009101000173 10. 0.15 1.380 1.3 0.3 1009101000174 1009101000175 10. 0.15 1.53 3.3 0.9 1009101000176 1. 1009101000177 10. 0.15 1.59 3.0 0.5 1009101000178 4. 1009101000179 10. 0.15 1.614 3.2 0.4 1009101000180 3. 1009101000181 10. 0.15 1.633 1.0 0.2 1009101000182 1009101000183 10. 0.15 1.659 0.7 0.3 1009101000184 1009101000185 10. 0.15 1.779 38.8 4.7 1009101000186 2. 1009101000187 10. 0.15 1.809 0.4 0.1 1009101000188 1009101000189 10. 0.15 1.963 0.9 0.3 1009101000190 1009101000191 10. 0.15 2.032 1.2 0.2 1009101000192 1009101000193 10. 0.15 2.203 2.232 1.5 0.3 1009101000194 1009101000195 10. 0.15 2.838 4.4 0.6 1009101000196 1009101000197 10. 0.15 3.196 1.1 0.3 1009101000198 1009101000199 10. 0.15 4.497 2.9 0.5 1009101000200 1009101000201 10. 0.15 5.1 5.2 0.8 1009101000202 1. 1009101000203 10. 0.15 5.6 2.1 0.5 1009101000204 1. 1009101000205 10. 0.15 6.878 4.2 0.6 1009101000206 1009101000207 10. 0.15 7.4 2.9 0.4 1009101000208 1. 1009101000209 10. 0.15 7.935 1.1 0.2 1009101000210 1009101000211 10. 0.15 8.3 0.6 0.1 1009101000212 1. 1009101000213 10. 0.15 8.941 0.5 0.1 1009101000214 1009101000215 11. 0.15 0.390 1.1 0.2 1009101000216 1009101000217 11. 0.15 0.585 2.9 0.4 1009101000218 1009101000219 11. 0.15 0.856 0.8 0.2 1009101000220 1009101000221 11. 0.15 0.942 1.1 0.2 1009101000222 1009101000223 11. 0.15 0.98 4.1 0.5 1009101000224 1. 1009101000225 11. 0.15 1.01 1.0 0.3 1009101000226 1009101000227 11. 0.15 1.113 0.7 0.3 1009101000228 1009101000229 11. 0.15 1.27 2.0 0.4 1009101000230 1. 1009101000231 11. 0.15 1.341 1.4 0.3 1009101000232 1009101000233 11. 0.15 1.380 1.2 0.4 1009101000234 1009101000235 11. 0.15 1.53 5.4 1.4 1009101000236 1. 1009101000237 11. 0.15 1.59 2.1 0.4 1009101000238 1. 1009101000239 11. 0.15 1.602 1.9 0.4 1009101000240 1009101000241 11. 0.15 1.614 3.7 0.6 1009101000242 1009101000243 11. 0.15 1.633 1.2 0.4 1009101000244 1009101000245 11. 0.15 1.659 0.7 0.3 1009101000246 1009101000247 11. 0.15 1.779 40.0 4.8 1009101000248 2. 1009101000249 11. 0.15 1.963 0.7 0.3 1009101000250 1009101000251 11. 0.15 2.032 1.6 0.3 1009101000252 1009101000253 11. 0.15 2.203 2.232 2.1 0.4 1009101000254 1009101000255 11. 0.15 2.27 1.8 0.4 1009101000256 1. 1009101000257 11. 0.15 2.838 6.6 0.9 1009101000258 1009101000259 11. 0.15 3.196 1.1 0.3 1009101000260 1009101000261 11. 0.15 4.497 2.2 0.5 1009101000262 1009101000263 11. 0.15 5.1 4.4 0.6 1009101000264 1. 1009101000265 11. 0.15 5.6 1.4 0.6 1009101000266 1. 1009101000267 11. 0.15 6.878 4.8 0.7 1009101000268 1009101000269 11. 0.15 7.4 2.8 0.4 1009101000270 1. 1009101000271 11. 0.15 7.935 1.7 0.3 1009101000272 1009101000273 11. 0.15 8.30 0.8 0.2 1009101000274 1. 1009101000275 11. 0.15 8.941 0.9 0.2 1009101000276 1009101000277 11. 0.15 8.941 1.0 0.2 1009101000278 1009101000279 ENDDATA 248 0 1009101000280 ENDSUBENT 279 0 1009101099999 ENDENTRY 10 0 1009199999999