ENTRY 13820 20020207 00001382000000001 SUBENT 13820001 20020207 00001382000100001 BIB 6 10 1382000100002 INSTITUTE (1USAANL) 1382000100003 REFERENCE (J,PR/C,3,1570,197104) 1382000100004 AUTHOR (J.Vervier,H.H.Bolotin) 1382000100005 TITLE Low-Lying Excited States of 70Ga and 72Ga Populated in 1382000100006 Thermal-Neutron Capture. 1382000100007 ADD-RES (DECAY) Constructed the decay scheme of low-lying 1382000100008 states in 70Ga and 72Ga. 1382000100009 Determined the neutron binding energies 7651(1) keV 1382000100010 for 70Ga and 6519(1) keV for 72Ga. 1382000100011 HISTORY (20020129C) IS+VM 1382000100012 ENDBIB 10 0 1382000100013 COMMON 1 3 1382000100014 EN-DUMMY 1382000100015 EV 1382000100016 0.0253 1382000100017 ENDCOMMON 3 0 1382000100018 ENDSUBENT 17 0 1382000199999 SUBENT 13820002 20020207 00001382000200001 BIB 12 53 1382000200002 REACTION (31-GA-69(N,G)31-GA-70,,SPC,,REL/SPA) 1382000200003 FACILITY (REAC,1USAANL) Argonne CP-5 reseach reactor tangential 1382000200004 through-tube facility which allows highly collimated 1382000200005 beam of gamma rays emitted by target to emerge from 1382000200006 reactor tube. Low-energy transitions strongly 1382000200007 attenuated in the neutron shielding material. 1382000200008 INC-SOURCE (REAC) Reactor core with a thermal-neutron flux ~3.E+131382000200009 neutrons/cm2/s at the sample position. 1382000200010 Slab of borated polyethylene placed between target and 1382000200011 detector in order to suppress thermal- and epithermal-1382000200012 neutron flux and to limit counting rate in detector 1382000200013 to a tolerable range (~2000 counts/sec). 1382000200014 INC-SPECT Reactor spectrum with cadmium ratio ~7. 1382000200015 SAMPLE Powder oxide Ga2O3 samples, enriched to 99.75% in 1382000200016 69Ga, weighing 4.0 g, encapsulated in high-purity 1382000200017 graphite sample holders and installed at center of 1382000200018 tangential through-tube facility. 1382000200019 METHOD Results obtained from 2 runs lasting 42 h. 1382000200020 Pair-spectrometer results obtained after 65-h running 1382000200021 time. 1382000200022 DETECTOR (GELI) 4-cm3 Ge(Li) spectrometer with energy resolution1382000200023 width of ~6 keV at 6-MeV deposited energy used in 1382000200024 singles gamma-ray spectroscopy 1382000200025 (BPAIR). Above Ge(Li) detector used as central detector1382000200026 with two 4x4-in NaI(T1) side crystals mounted 180 1382000200027 degrees apart. 1382000200028 MONITOR Energy calibration based on the carbon ground-state 1382000200029 neutron-capture gamma-ray at 4945.46(17) keV, present 1382000200030 due to graphite sample holder. 1382000200031 Relative detection efficiency for double-escape peaks 1382000200032 determined empirically as a function of gamma-ray 1382000200033 energy using nitrogen neutron-capture gamma-ray 1382000200034 spectrum and known relative intensities of its 1382000200035 various components. 1382000200036 Relative intensities normalized to 6391-keV line 1382000200037 which was arbitrarily taken as 3.03 photons per 1382000200038 100 neutron captures. Value obtained by Rasmussen 1382000200039 et al. (unpublished, MIT) for absolute intensity of 1382000200040 the same line in natural gallium. 1382000200041 ANALYSIS Minimization program used for analyzing spectra by 1382000200042 fitting the peaks with a Gaussian line shape plus a 1382000200043 linear background. 1382000200044 Due to spectral complexities and other uncertainties 1382000200045 encountered for transitions energies < 4.5 MeV, 1382000200046 capture gamma-ray spectra below this energy were 1382000200047 not analyzed in detail. 1382000200048 ERR-ANALYS (E-ERR) Uncertainties in gamma-ray energies. 1382000200049 (DATA-ERR) Uncertainties of line intensities includes 1382000200050 ~15% uncertainty in line intensities in nitrogen used 1382000200051 in to determine relative double-escape-peak detector 1382000200052 efficiences of Ge(Li) detector. 1382000200053 FLAG (1.) Doubtful line. 1382000200054 STATUS Data taken from Table I of reference. 1382000200055 ENDBIB 53 0 1382000200056 COMMON 1 3 1382000200057 E-NRM 1382000200058 KEV 1382000200059 6391. 1382000200060 ENDCOMMON 3 0 1382000200061 DATA 5 101 1382000200062 E E-ERR DATA DATA-ERR FLAG 1382000200063 KEV KEV ARB-UNITS ARB-UNITS NO-DIM 1382000200064 7651. 1. 0.37 0.06 1382000200065 7144. 2. 0.05 0.01 1. 1382000200066 6999. 1. 1.64 0.25 1382000200067 6959. 1. 0.10 0.02 1382000200068 6656. 2. 0.41 0.06 1382000200069 6639. 2. 0.10 0.02 1382000200070 6629. 1. 0.38 0.06 1382000200071 6510. 1. 2.47 0.42 1382000200072 6449. 1. 0.22 0.03 1382000200073 6401. 2. 0.34 0.05 1382000200074 6391. 3. 3.03 1382000200075 6346. 2. 1.19 0.18 1382000200076 6341. 2. 0.59 0.10 1382000200077 6293. 1. 0.39 0.06 1382000200078 6239. 1. 0.34 0.05 1382000200079 6207. 1. 0.42 0.06 1382000200080 6196. 1. 0.50 0.08 1382000200081 6135. 1. 0.79 0.12 1382000200082 6120. 1. 0.61 0.09 1382000200083 6098. 1. 0.61 0.09 1382000200084 6031. 1. 0.11 0.02 1382000200085 6020. 1. 0.13 0.02 1382000200086 5961. 1. 0.18 0.03 1382000200087 5933. 1. 0.19 0.03 1. 1382000200088 5927. 1. 0.52 0.08 1382000200089 5918. 1. 0.15 0.03 1382000200090 5859. 1. 0.29 0.05 1382000200091 5829. 1. 0.41 0.06 1382000200092 5807. 2. 1.28 0.19 1382000200093 5787. 2. 0.08 0.02 1. 1382000200094 5747. 2. 0.84 0.13 1382000200095 5723. 2. 0.48 0.08 1382000200096 5716. 2. 0.12 0.02 1382000200097 5683. 1. 0.29 0.05 1382000200098 5669. 1. 0.35 0.06 1382000200099 5637. 2. 0.36 0.06 1382000200100 5627. 2. 1.02 0.16 1382000200101 5579. 1. 0.43 0.07 1382000200102 5539. 2. 0.77 0.12 1382000200103 5511. 2. 0.46 0.07 1382000200104 5489. 1. 1.86 0.28 1382000200105 5464. 2. 0.08 0.02 1382000200106 5440. 2. 0.19 0.03 1382000200107 5420. 2. 0.06 0.02 1382000200108 5399. 2. 0.22 0.04 1382000200109 5342. 2. 0.15 0.03 1382000200110 5334. 1. 0.49 0.08 1382000200111 5312. 1. 0.37 0.06 1382000200112 5302. 1. 0.30 0.05 1382000200113 5272. 1. 0.35 0.05 1382000200114 5265. 1. 0.10 0.02 1. 1382000200115 5244. 1. 0.11 0.02 1382000200116 5223. 1. 0.34 0.06 1382000200117 5215. 1. 0.23 0.04 1382000200118 5193. 1. 0.31 0.06 1. 1382000200119 5189. 1. 0.51 0.08 1382000200120 5176. 1. 0.36 0.06 1382000200121 5143. 2. 0.04 0.01 1382000200122 5133. 1. 0.78 0.12 1382000200123 5105. 2. 0.24 0.05 1382000200124 5096. 2. 0.18 0.04 1382000200125 5082. 1. 0.80 0.12 1382000200126 5072. 2. 0.29 0.06 1. 1382000200127 5068. 1. 0.35 0.07 1382000200128 5051. 1. 0.20 0.04 1382000200129 5038. 1. 0.38 0.06 1382000200130 5029. 2. 0.11 0.02 1382000200131 5003. 2. 0.15 0.04 1. 1382000200132 4999. 1. 0.70 0.11 1382000200133 4979. 2. 0.28 0.06 1382000200134 4956. 2. 1.33 0.20 1382000200135 4922. 1. 0.14 0.03 1382000200136 4910. 2. 0.25 0.04 1382000200137 4896. 2. 0.09 0.02 1382000200138 4872. 2. 0.17 0.03 1382000200139 4863. 1. 0.63 0.10 1382000200140 4853. 2. 0.43 0.08 1382000200141 4842. 2. 0.28 0.05 1382000200142 4823. 1. 1.06 0.16 1382000200143 4813. 2. 0.26 0.05 1382000200144 4796. 2. 0.13 0.03 1382000200145 4779. 2. 0.18 0.05 1382000200146 4773. 3. 0.16 0.04 1382000200147 4753. 1. 0.84 0.13 1382000200148 4721. 1. 0.22 0.03 1382000200149 4711. 1. 1.12 0.18 1382000200150 4696. 1. 1.48 0.22 1382000200151 4682. 3. 0.06 0.02 1382000200152 4672. 1. 0.10 0.02 1382000200153 4660. 3. 0.02 0.01 1. 1382000200154 4631. 1. 0.13 0.03 1382000200155 4620. 2. 0.06 0.01 1. 1382000200156 4596. 1. 0.39 0.06 1382000200157 4589. 2. 0.15 0.03 1382000200158 4581. 2. 0.16 0.03 1382000200159 4571. 2. 0.18 0.03 1382000200160 4565. 2. 0.11 0.02 1382000200161 4547. 2. 0.20 0.03 1382000200162 4525. 2. 0.09 0.02 1382000200163 4511. 2. 0.07 0.02 1382000200164 4501. 2. 0.10 0.02 1382000200165 ENDDATA 103 0 1382000200166 ENDSUBENT 165 0 1382000299999 SUBENT 13820003 20020207 00001382000300001 BIB 12 53 1382000300002 REACTION (31-GA-71(N,G)31-GA-72,,SPC,,REL/SPA) 1382000300003 FACILITY (REAC,1USAANL) Argonne CP-5 reseach reactor tangential 1382000300004 through-tube facility which allows highly collimated 1382000300005 beam of gamma rays emitted by target to emerge from 1382000300006 reactor tube. Low-energy transitions strongly 1382000300007 attenuated in the neutron shielding material. 1382000300008 INC-SOURCE (REAC) Reactor core with a thermal-neutron flux ~3.E+131382000300009 neutrons/cm2/s at the sample position. 1382000300010 Slab of borated polyethylene placed between target and 1382000300011 detector in order to suppress thermal- and epithermal-1382000300012 neutron flux and to limit counting rate in detector 1382000300013 to a tolerable range (~2000 counts/sec). 1382000300014 INC-SPECT Reactor spectrum with cadmium ratio ~7. 1382000300015 SAMPLE Powder oxide Ga2O3 samples, enriched to 99.61% in 1382000300016 71Ga, weighing 1.3 g, encapsulated in high-purity 1382000300017 graphite sample holders and installed at center of 1382000300018 tangential through-tube facility. 1382000300019 METHOD Results obtained in 3 runs lasting a total of 65 h. 1382000300020 Pair-spectrometer data obtained after 61-h running 1382000300021 time. 1382000300022 DETECTOR (GELI) 14-cm3 Ge(Li) spectrometer with energy resolutio1382000300023 width of ~6 keV at 6-MeV deposited energy used in 1382000300024 singles gamma-ray spectroscopy 1382000300025 Above Ge(Li) detector used as central detector in pair 1382000300026 spectrometer with two 4x4-in NaI(T1) side crystals 1382000300027 mounted 180 degrees apart. 1382000300028 ANALYSIS Minimization program used for analyzing spectra by 1382000300029 fitting the peaks with a Gaussian line shape plus a 1382000300030 linear background. 1382000300031 Due to spectral complexities and other uncertainties 1382000300032 encountered for transitions energies < 4.5 MeV, 1382000300033 capture gamma-ray spectra below this energy were 1382000300034 not analyzed in detail. 1382000300035 MONITOR Energy calibration based on the carbon ground-state 1382000300036 neutron-capture gamma-ray at 4945.46(17) keV, present 1382000300037 due to graphite sample holder. 1382000300038 Relative detection efficiency for double-escape peaks 1382000300039 determined empirically as a function of gamma-ray 1382000300040 energy using nitrogen neutron-capture gamma-ray 1382000300041 spectrum and known relative intensities of its 1382000300042 various components. 1382000300043 Relative intensities normalized to 6359-keV line 1382000300044 which was arbitrarily taken as 12.09 photons per 1382000300045 100 neutron captures - value obtained by Rasmussen 1382000300046 et al. (unpublished, MIT) for absolute intensity of 1382000300047 the same line in natural gallium. 1382000300048 ERR-ANALYS (E-ERR) Uncertainties in gamma-ray energies; 1382000300049 (DATA-ERR) Uncertainties in intensities, including 1382000300050 ~15% uncertainty of line intensities in nitrogen used 1382000300051 in determination of relative double-escape-peak 1382000300052 detector efficiences. 1382000300053 FLAG (1.) Doubtful line. 1382000300054 STATUS Data taken from Table II of reference. 1382000300055 ENDBIB 53 0 1382000300056 COMMON 1 3 1382000300057 E-NRM 1382000300058 KEV 1382000300059 6359. 1382000300060 ENDCOMMON 3 0 1382000300061 DATA 5 82 1382000300062 E E-ERR DATA DATA-ERR FLAG 1382000300063 KEV KEV ARB-UNITS ARB-UNITS NO-DIM 1382000300064 6519. 1. 1.97 0.30 1382000300065 6503. 1. 0.42 0.06 1382000300066 6401. 1. 0.29 0.04 1382000300067 6392. 2. 0.26 0.04 1382000300068 6359. 1. 12.09 1382000300069 6322. 2. 1.59 0.24 1382000300070 6310. 2. 2.01 0.36 1382000300071 6290. 2. 0.14 0.02 1382000300072 6271. 2. 0.12 0.02 1382000300073 6237. 2. 0.34 0.05 1382000300074 6190. 2. 1.64 0.25 1382000300075 6128. 2. 2.38 0.36 1382000300076 6110. 1. 5.96 0.90 1382000300077 6007. 1. 6.30 0.94 1382000300078 5956. 2. 0.38 0.06 1382000300079 5919. 1. 1.61 0.24 1382000300080 5901. 1. 1.94 0.29 1382000300081 5883. 1. 1.13 0.17 1382000300082 5871. 2. 0.24 0.04 1382000300083 5780. 3. 2.09 0.32 1382000300084 5721. 2. 0.24 0.04 1. 1382000300085 5691. 1. 2.38 0.36 1382000300086 5663. 1. 1.24 0.19 1382000300087 5650. 1. 1.71 0.26 1382000300088 5643. 2. 0.78 0.12 1382000300089 5626. 2. 0.08 0.02 1. 1382000300090 5601. 1. 7.13 1.08 1382000300091 5541. 2. 1.13 0.17 1382000300092 5498. 2. 0.28 0.05 1382000300093 5487. 2. 1.07 0.16 1382000300094 5469. 2. 0.34 0.06 1382000300095 5460. 2. 0.49 0.12 1. 1382000300096 5443. 2. 0.19 0.04 1. 1382000300097 5404. 2. 0.39 0.06 1382000300098 5390. 2. 0.31 0.05 1382000300099 5370. 2. 0.27 0.05 1382000300100 5339. 1. 4.52 0.68 1382000300101 5333. 1. 2.46 0.37 1382000300102 5319. 2. 0.23 0.04 1382000300103 5314. 2. 0.18 0.04 1. 1382000300104 5303. 2. 0.14 0.02 1. 1382000300105 5282. 2. 0.15 0.03 1. 1382000300106 5271. 2. 0.29 0.05 1382000300107 5257. 1. 0.52 0.08 1382000300108 5234. 1. 4.27 0.64 1382000300109 5223. 1. 1.96 0.30 1382000300110 5196. 1. 4.53 0.68 1382000300111 5160. 1. 1.71 0.27 1382000300112 5124. 2. 0.40 0.07 1382000300113 5092. 3. 0.85 0.13 1382000300114 5078. 2. 0.28 0.05 1382000300115 5054. 1. 1.13 0.17 1382000300116 5047. 2. 0.32 0.05 1. 1382000300117 5031. 2. 0.20 0.04 1. 1382000300118 5015. 2. 0.42 0.09 1382000300119 5004. 2. 0.30 0.05 1382000300120 4987. 2. 0.28 0.05 1382000300121 4907. 2. 0.12 0.03 1382000300122 4890. 1. 2.46 0.38 1382000300123 4867. 1. 2.35 0.38 1382000300124 4839. 1. 4.90 0.73 1382000300125 4806. 2. 0.37 0.06 1382000300126 4792. 1. 2.44 0.36 1382000300127 4770. 2. 0.20 0.03 1382000300128 4761. 1. 1.06 0.16 1382000300129 4743. 2. 0.07 0.02 1. 1382000300130 4729. 2. 0.25 0.04 1382000300131 4718. 2. 0.53 0.10 1382000300132 4704. 2. 0.47 0.07 1382000300133 4686. 2. 0.83 0.13 1382000300134 4678. 2. 0.41 0.07 1382000300135 4664. 2. 0.42 0.07 1382000300136 4650. 2. 0.42 0.07 1382000300137 4638. 2. 0.15 0.03 1382000300138 4622. 2. 0.50 0.09 1382000300139 4607. 3. 0.07 0.03 1. 1382000300140 4602. 2. 0.25 0.06 1382000300141 4595. 2. 0.33 0.07 1382000300142 4578. 1. 0.69 0.11 1382000300143 4543. 1. 1.28 0.21 1382000300144 4512. 3. 0.12 0.04 1. 1382000300145 4501. 1. 0.64 0.10 1382000300146 ENDDATA 84 0 1382000300147 ENDSUBENT 146 0 1382000399999 SUBENT 13820004 20020207 00001382000400001 BIB 9 17 1382000400002 REACTION (31-GA-71(N,G)31-GA-72,,SPC,,REL/MXW) 1382000400003 FACILITY (REAC,1USAANL) Argonne CP-5 reseach reactor external- 1382000400004 beam facility. 1382000400005 INC-SOURCE (THCOL) Highly collimated external beam of thermal 1382000400006 neutrons. 1382000400007 INC-SPECT Thermal spectrum (cadmium ratio ~550). 1382000400008 SAMPLE 33-mg sample of Ga metal enriched to 99.61% in 71Ga. 1382000400009 DETECTOR (GELI) 20-cm3 Ge(Li) spectrometer with energy resolutio1382000400010 width of 2.6 keV at 1.3-MeV deposited energy. 1382000400011 MONITOR Energies determined relative to gamma-rays at 1382000400012 121.970(30) and 661.635(17) keV from decay of 57Co and1382000400013 Cs137, respectively. 1382000400014 Relative intensities normalized to 145.09-keV line, 1382000400015 taken as 100. 1382000400016 ERR-ANALYS (E-ERR) Uncertainties in gamma-ray energies. 1382000400017 (DATA-ERR) Approximate intensity uncertainties. 1382000400018 STATUS Data taken from Table III of reference. 1382000400019 ENDBIB 17 0 1382000400020 COMMON 1 3 1382000400021 E-NRM 1382000400022 KEV 1382000400023 149.09 1382000400024 ENDCOMMON 3 0 1382000400025 DATA 4 108 1382000400026 E E-ERR DATA DATA-ERR 1382000400027 KEV KEV ARB-UNITS PER-CENT 1382000400028 668.50 0.14 1.3 20. 1382000400029 660.02 0.17 2.5 20. 1382000400030 658.31 0.24 1.2 20. 1382000400031 650.36 0.76 0.3 20. 1382000400032 645.93 0.29 1.3 20. 1382000400033 643.03 0.29 1.4 20. 1382000400034 637.91 0.25 1.4 20. 1382000400035 630.30 0.04 6.7 10. 1382000400036 623.69 0.30 1.2 20. 1382000400037 621.88 0.39 0.9 20. 1382000400038 619.12 0.46 1.0 20. 1382000400039 617.70 0.41 0.5 20. 1382000400040 613.68 0.24 0.7 20. 1382000400041 608.77 0.61 0.3 20. 1382000400042 603.38 0.19 1.8 20. 1382000400043 601.40 0.11 3.6 20. 1382000400044 596.26 0.05 3.5 20. 1382000400045 589.68 0.84 0.3 20. 1382000400046 587.14 0.36 1.1 20. 1382000400047 585.38 0.36 1.1 20. 1382000400048 582.29 0.55 0.5 20. 1382000400049 579.80 0.54 0.7 20. 1382000400050 572.03 0.32 0.6 20. 1382000400051 569.73 0.32 0.6 20. 1382000400052 564.54 0.20 1.1 20. 1382000400053 561.08 0.54 0.5 20. 1382000400054 559.31 0.43 0.5 20. 1382000400055 555.5 1.0 0.2 20. 1382000400056 549.94 0.70 0.3 20. 1382000400057 547.86 0.27 1.4 20. 1382000400058 545.06 0.13 1.7 20. 1382000400059 538.07 0.32 0.9 20. 1382000400060 535.61 0.08 4.3 20. 1382000400061 532.39 0.50 0.4 20. 1382000400062 527.61 0.16 2.2 20. 1382000400063 525.76 0.50 0.3 20. 1382000400064 500.33 0.10 1.1 20. 1382000400065 497.75 0.26 0.5 20. 1382000400066 488.81 0.04 3.2 20. 1382000400067 465.35 0.04 7.3 10. 1382000400068 461.31 0.17 1.6 20. 1382000400069 458.68 0.15 1.8 20. 1382000400070 444.68 0.44 4.1 20. 1382000400071 442.40 0.57 0.4 20. 1382000400072 439.33 0.13 1.9 20. 1382000400073 436.26 0.22 1.4 20. 1382000400074 433.76 0.29 0.9 20. 1382000400075 431.62 0.67 0.3 20. 1382000400076 423.78 0.26 0.6 20. 1382000400077 415.91 0.32 0.4 20. 1382000400078 411.28 0.05 3.7 20. 1382000400079 408.09 0.09 2.7 20. 1382000400080 406.20 0.15 1.0 20. 1382000400081 402.85 0.06 2.4 20. 1382000400082 393.26 0.04 12.7 10. 1382000400083 390.72 0.04 7.3 10. 1382000400084 384.34 0.16 0.8 20. 1382000400085 379.69 0.42 0.3 20. 1382000400086 376.40 0.05 4.1 20. 1382000400087 373.59 0.46 0.2 20. 1382000400088 368.07 0.34 0.4 20. 1382000400089 355.58 0.12 0.7 20. 1382000400090 353.39 0.13 0.7 20. 1382000400091 351.51 0.14 0.5 20. 1382000400092 318.11 0.50 0.8 20. 1382000400093 315.76 0.31 2.9 20. 1382000400094 313.82 0.14 4.0 20. 1382000400095 308.95 0.37 1.1 20. 1382000400096 306.14 0.16 2.9 20. 1382000400097 302.61 0.04 10.3 10. 1382000400098 298.13 0.27 1.1 20. 1382000400099 276.36 0.05 7.5 10. 1382000400100 273.92 0.33 1.0 20. 1382000400101 266.13 0.04 6.8 10. 1382000400102 264.06 0.04 4.5 20. 1382000400103 257.33 0.04 3.3 20. 1382000400104 252.41 0.46 0.4 20. 1382000400105 248.97 0.04 23.7 10. 1382000400106 246.84 0.24 2.0 20. 1382000400107 236.24 0.17 1.3 20. 1382000400108 231.02 0.19 2.1 20. 1382000400109 228.88 0.07 8.2 10. 1382000400110 218.67 0.33 0.6 20. 1382000400111 212.20 0.07 15.5 10. 1382000400112 210.33 0.19 3.6 20. 1382000400113 202.08 0.20 2.3 20. 1382000400114 197.92 0.04 27.4 10. 1382000400115 194.62 0.05 21.2 10. 1382000400116 191.98 0.04 39.0 10. 1382000400117 184.05 0.04 19.6 10. 1382000400118 181.57 0.04 8.1 10. 1382000400119 165.51 0.04 34.8 10. 1382000400120 163.16 0.09 4.0 20. 1382000400121 153.76 0.04 6.0 10. 1382000400122 145.09 0.04 100. 10. 1382000400123 142.32 0.34 3.7 20. 1382000400124 139.63 0.25 3.1 20. 1382000400125 135.95 0.42 2.0 20. 1382000400126 132.43 0.25 2.7 20. 1382000400127 128.45 0.37 1.6 20. 1382000400128 120.99 0.04 2.2 20. 1382000400129 116.81 0.77 0.5 20. 1382000400130 112.42 0.04 30.6 10. 1382000400131 109.92 0.18 3.1 20. 1382000400132 106.36 0.13 2.9 20. 1382000400133 103.23 0.05 10.2 10. 1382000400134 88.85 0.07 5.4 10. 1382000400135 79.89 0.10 4.8 20. 1382000400136 ENDDATA 110 0 1382000400137 ENDSUBENT 136 0 1382000499999 ENDENTRY 4 0 1382099999999