ENTRY 14423 20200116 14621442300000001 SUBENT 14423001 20200116 14621442300100001 BIB 10 57 1442300100002 TITLE Exploratory study of fission product yields of 1442300100003 neutron-induced fission of 235U, 238U, and 239Pu at 1442300100004 8.9 MeV 1442300100005 AUTHOR (C.Bhatia,B.F.Fallin,M.E.Gooden,C.R.Howell,J.H.Kelley, 1442300100006 W.Tornow,C.W.Arnold,E.Bond,T.A.Bredeweg,M.M.Fowler, 1442300100007 W.Moody,R.S.Rundberg,G.Y.Rusev,D.J.Vieira,J.B.Wilhelmy,1442300100008 J.A.Becker,R.Macri,C.Ryan,S.A.Sheets,M.A.Stoyer, 1442300100009 A.P.Tonchev) 1442300100010 INSTITUTE (1USADKE,1USATNL,1USANCS,1USALAS,1USALRL) 1442300100011 REFERENCE (J,PR/C,91,064604,2015) 1442300100012 #NSR: 2015BH09 1442300100013 #doi:10.1103/PhysRevC.91.064604 1442300100014 (J,NDS,119,324,2014) 1442300100015 #NSR: 2014BH11 1442300100016 #doi:10.1016/j.nds.2014.08.089 1442300100017 FACILITY (VDGT,1USATNL) Experiment performed using High-Voltage 1442300100018 Engineering Model FN Tandem Van de Graaff accelerator 1442300100019 at the Triangle Universities Nuclear Laboratory 1442300100020 DETECTOR (FISCH) Dual fission chambers, located at 2.54 cm 1442300100021 from the front side of gas cell. Activation foil was 1442300100022 located in the center of the chamber. The efficiency 1442300100023 of the dual-fission chambers of the present design 1442300100024 was 98.5%. 1442300100025 (HPGE) Gamma rays from fission products were measured 1442300100026 using HPGE detectors with 60 % efficiency, located 1442300100027 at TUNL's Low-Background Counting Facility 1442300100028 METHOD (ACTIV) Fission yields were determined by activation 1442300100029 method using characteristic gamma rays of fission 1442300100030 products. 1442300100031 INC-SOURCE (D-D) An unpulsed 2 mu-A deuteron beam of energy 6.40 1442300100032 MeV enters through a 6.5 mu-m Havar foil the gas 1442300100033 cell. the resulting 6.0-MeV deuteron beam enters a 1442300100034 3.0-cm long cell filled with 6.9 atm of high-purity 1442300100035 deuterium gas. In traversing the gas cell the 1442300100036 deuterium beam loses < 0.53 MeV in the gas and is 1442300100037 then stopped in a 0.3-mm-thick tantalum disk at the 1442300100038 end of the gas cell. The resulting neutron beam from 1442300100039 the 2H(d,n) 3He reaction at 0 deg has a calculated 1442300100040 mean energy of 9.00 MeV with an energy spread of 0.54 1442300100041 MeV (FWHM). Neutrons of 4.6 MeV were produced via the 1442300100042 2H(d,n)3He reaction. 1442300100043 CORRECTION Data were corrected for 1442300100044 i) neutron flux differences on sample and reference 1442300100045 oil caused by close geometry (up to 10%) 1442300100046 ii) efficiencies of dual-fission chamber caused 1442300100047 by the center-of-mass motion (0.8%) 1442300100048 iii) change in the effective fission cross section 1442300100049 due to the isotopic content of the target 1442300100050 relative to that of the reference foil (1%) 1442300100051 iv) dead time correction (1%) 1442300100052 v) off-energy neutron contribution (typically 0.5%)1442300100053 vi) summing 1442300100054 HISTORY (20150722C) Compiled by S.H. 1442300100055 (20190604A) OG. 2nd ref. added. #NSR and #doi added. 1442300100056 COMMON,DECAY-DATA,ERR-ANALYS from Sub001 -> Sub002-004.1442300100057 Sub005-Sub007 added. 1442300100058 (20200104A) OS. REACTION in sub.2 corrected 1442300100059 ENDBIB 57 0 1442300100060 NOCOMMON 0 0 1442300100061 ENDSUBENT 60 0 1442300199999 SUBENT 14423002 20200116 14621442300200001 BIB 6 32 1442300200002 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY) 1442300200003 2((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 1442300200004 (92-U-235(N,F)42-MO-99,CUM,FY)) 1442300200005 3((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 1442300200006 (92-U-235(N,F)56-BA-140,CUM,FY)) 1442300200007 SAMPLE (92-U-235,ENR=0.9327) 1442300200008 (92-U-234,ENR=0.0105) 1442300200009 (92-U-238,ENR=0.0568) 1442300200010 Enriched 235U sample with mass 233.02 mg 1442300200011 and diameter 12.35 mm 1442300200012 DECAY-DATA ((1.)38-SR-92,2.611HR,DG,1383.93,0.90) 1442300200013 ((2.)40-ZR-97,16.749HR,DG,743.36,0.9309) 1442300200014 ((3.)42-MO-99,65.976HR,DG,739.500,0.1226) 1442300200015 ((4.)44-RU-105,4.44HR,DG,724.30,0.473) 1442300200016 ((5.)52-TE-132,3.204D,DG,228.16,0.88) 1442300200017 ((7.)56-BA-140,12.7527D,DG,537.261,0.2439) 1442300200018 ((8.)58-CE-143,33.039HR,DG,293.266,0.428) 1442300200019 ((9.)60-ND-147,10.98D,DG,531.016,0.1337) 1442300200020 ERR-ANALYS (ERR-S) Statistical uncertainty 1442300200021 (ERR-T) Total uncertainty 1442300200022 (ERR-1,0.18,2.1) Statist. uncertainty of gamma counts 1442300200023 (ERR-3,0.51,3.79) Uncert. in gamma ray detector effic. 1442300200024 (ERR-4,0.2,3.0) Uncertainty in summing correction 1442300200025 (ERR-5) Uncertainty in FC1, FC2 counts 1442300200026 (ERR-6) Uncertainty in target mass 1442300200027 (ERR-7) Uncertainty in target diameter 1442300200028 (ERR-8) Uncertainty in fission chamber efficiency 1442300200029 (ERR-9) Uncertainty in total average fission counts 1442300200030 (ERR-10) Uncertainty in number of break-up neutrons 1442300200031 (ERR-11,1.3,4.1) Total reduced yield uncertainty 1442300200032 STATUS (TABLE) Data taken from tab. 4 of the main reference 1442300200033 HISTORY (20200104A) REACTION 3: Projectile changed to N 1442300200034 ENDBIB 32 0 1442300200035 COMMON 8 6 1442300200036 EN EN-RSL-FW ERR-5 ERR-6 ERR-7 ERR-8 1442300200037 ERR-9 ERR-10 1442300200038 MEV MEV PER-CENT PER-CENT PER-CENT PER-CENT 1442300200039 PER-CENT PER-CENT 1442300200040 8.9 0.54 0.088 8.96E-3 0.404 1.53 1442300200041 2.0 0.2 1442300200042 ENDCOMMON 6 0 1442300200043 DATA 12 8 1442300200044 ELEMENT MASS DATA 1ERR-S 1ERR-T 1DATA 21442300200045 ERR-S 2ERR-T 2DATA 3ERR-S 3ERR-T 3DECAY-FLAG 1442300200046 NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS NO-DIM 1442300200047 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1442300200048 38.0 92.0 4.38 0.07 0.31 0.934 1442300200049 0.013 0.069 0.882 0.036 0.071 1. 1442300200050 40.0 97.0 5.11 0.11 0.15 1.089 1442300200051 0.008 0.039 1.029 0.016 0.048 2. 1442300200052 42.0 99.0 4.69 0.10 0.16 1442300200053 0.945 0.014 0.048 3. 1442300200054 44.0 105.0 0.58 0.02 0.02 0.123 1442300200055 0.003 0.005 0.116 0.003 0.006 4. 1442300200056 52.0 132.0 3.61 0.43 0.45 0.771 1442300200057 0.109 0.098 0.728 0.079 0.095 5. 1442300200058 56.0 140.0 4.96 0.20 0.23 1.059 1442300200059 0.016 0.053 7. 1442300200060 58.0 143.0 4.29 0.35 0.36 0.916 1442300200061 0.070 0.080 0.865 0.048 0.080 8. 1442300200062 60.0 147.0 1.81 0.02 0.05 0.386 1442300200063 0.005 0.014 0.364 0.004 0.017 9. 1442300200064 ENDDATA 20 0 1442300200065 ENDSUBENT 64 0 1442300299999 SUBENT 14423003 20190604 14571442300300001 BIB 5 30 1442300300002 REACTION 1(92-U-238(N,F)ELEM/MASS,CUM,FY) 1442300300003 2((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 1442300300004 (92-U-238(N,F)42-MO-99,CUM,FY)) 1442300300005 3((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 1442300300006 (92-U-238(N,F)56-BA-140,CUM,FY)) 1442300300007 SAMPLE (92-U-235,ENR=0.00026) 1442300300008 (92-U-238,ENR=0.99974) 1442300300009 Enriched 238U sample with mass 441.93 mg 1442300300010 and diameter 12.42 mm 1442300300011 DECAY-DATA ((1.)38-SR-92,2.611HR,DG,1383.93,0.90) 1442300300012 ((2.)40-ZR-97,16.749HR,DG,743.36,0.9309) 1442300300013 ((3.)42-MO-99,65.976HR,DG,739.500,0.1226) 1442300300014 ((4.)44-RU-105,4.44HR,DG,724.30,0.473) 1442300300015 ((5.)52-TE-132,3.204D,DG,228.16,0.88) 1442300300016 ((7.)56-BA-140,12.7527D,DG,537.261,0.2439) 1442300300017 ((8.)58-CE-143,33.039HR,DG,293.266,0.428) 1442300300018 ((9.)60-ND-147,10.98D,DG,531.016,0.1337) 1442300300019 ERR-ANALYS (ERR-S) Statistical uncertainty 1442300300020 (ERR-T) Total uncertainty 1442300300021 (ERR-1,0.36,3.5) Statist. uncertainty of gamma counts 1442300300022 (ERR-3,0.56,1.60) Uncert. in gamma ray detector effic. 1442300300023 (ERR-4,0.2,3.0) Uncertainty in summing correction 1442300300024 (ERR-5) Uncertainty in FC1, FC2 counts 1442300300025 (ERR-6) Uncertainty in target mass 1442300300026 (ERR-7) Uncertainty in target diameter 1442300300027 (ERR-8) Uncertainty in fission chamber efficiency 1442300300028 (ERR-9) Uncertainty in total average fission counts 1442300300029 (ERR-10) Uncertainty in number of break-up neutrons 1442300300030 (ERR-11,2.3,4.4) Total reduced yield uncertainty 1442300300031 STATUS (TABLE) Data taken from tab. 5 of the main reference 1442300300032 ENDBIB 30 0 1442300300033 COMMON 8 6 1442300300034 EN EN-RSL-FW ERR-5 ERR-6 ERR-7 ERR-8 1442300300035 ERR-9 ERR-10 1442300300036 MEV MEV PER-CENT PER-CENT PER-CENT PER-CENT 1442300300037 PER-CENT PER-CENT 1442300300038 8.9 0.54 0.130 1.35E-4 0.403 1.50 1442300300039 2.16 0.2 1442300300040 ENDCOMMON 6 0 1442300300041 DATA 12 8 1442300300042 ELEMENT MASS DATA 1ERR-S 1ERR-T 1DATA 21442300300043 ERR-S 2ERR-T 2DATA 3ERR-S 3ERR-T 3DECAY-FLAG 1442300300044 NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS NO-DIM 1442300300045 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1442300300046 38.0 92.0 3.94 0.11 0.31 0.640 1442300300047 0.013 0.047 0.618 0.014 0.044 1. 1442300300048 40.0 97.0 5.52 0.14 0.21 0.897 1442300300049 0.016 0.024 0.866 0.012 0.019 2. 1442300300050 42.0 99.0 6.16 0.15 0.28 1442300300051 0.966 0.020 0.031 3. 1442300300052 44.0 105.0 1.85 0.05 0.08 0.300 1442300300053 0.007 0.010 0.290 0.006 0.008 4. 1442300300054 52.0 132.0 5.12 0.15 0.27 0.831 1442300300055 0.021 0.038 0.803 0.017 0.034 5. 1442300300056 56.0 140.0 6.38 0.18 0.27 1.035 1442300300057 0.021 0.033 7. 1442300300058 58.0 143.0 4.39 0.13 0.19 0.712 1442300300059 0.016 0.023 0.688 0.013 0.020 8. 1442300300060 60.0 147.0 2.69 0.12 0.15 0.437 1442300300061 0.017 0.022 0.422 0.000 0.020 9. 1442300300062 ENDDATA 20 0 1442300300063 ENDSUBENT 62 0 1442300399999 SUBENT 14423004 20190604 14571442300400001 BIB 5 32 1442300400002 REACTION 1(94-PU-239(N,F)ELEM/MASS,CUM,FY) 1442300400003 2((94-PU-239(N,F)ELEM/MASS,CUM,FY)/ 1442300400004 (94-PU-239(N,F)42-MO-99,CUM,FY)) 1442300400005 3((94-PU-239(N,F)ELEM/MASS,CUM,FY)/ 1442300400006 (94-PU-239(N,F)56-BA-140,CUM,FY)) 1442300400007 SAMPLE (94-PU-239,ENR=0.9841) 1442300400008 (94-PU-240,ENR=0.0158) 1442300400009 (94-PU-241,ENR=0.00003) 1442300400010 (94-PU-242,ENR=0.00003) 1442300400011 Two enriched 239Pu samples with mass 233.0, 1442300400012 233.7mg and diameter 12.39, 12.40 mm, respectively 1442300400013 DECAY-DATA ((1.)38-SR-92,2.611HR,DG,1383.93,0.90) 1442300400014 ((2.)40-ZR-97,16.749HR,DG,743.36,0.9309) 1442300400015 ((3.)42-MO-99,65.976HR,DG,739.500,0.1226) 1442300400016 ((4.)44-RU-105,4.44HR,DG,724.30,0.473) 1442300400017 ((5.)52-TE-132,3.204D,DG,228.16,0.88) 1442300400018 ((6.)53-I-133-G,20.83HR,DG,529.872,0.870) 1442300400019 ((7.)56-BA-140,12.7527D,DG,537.261,0.2439) 1442300400020 ((8.)58-CE-143,33.039HR,DG,293.266,0.428) 1442300400021 ((9.)60-ND-147,10.98D,DG,531.016,0.1337) 1442300400022 ERR-ANALYS (ERR-S) Statistical uncertainty 1442300400023 (ERR-T) Total uncertainty 1442300400024 (ERR-3,1.85,3.30) Uncert. in gamma ray detector effic. 1442300400025 (ERR-4,0.2,3.0) Uncertainty in summing correction 1442300400026 (ERR-5) Uncertainty in FC1, FC2 counts 1442300400027 (ERR-6) Uncertainty in target mass 1442300400028 (ERR-7) Uncertainty in target diameter 1442300400029 (ERR-8) Uncertainty in fission chamber efficiency 1442300400030 (ERR-9) Uncertainty in total average fission counts 1442300400031 (ERR-10) Uncertainty in number of break-up neutrons 1442300400032 (ERR-11,2.1,4.0) Total reduced yield uncertainty 1442300400033 STATUS (TABLE) Data taken from tab. 6 of the main reference 1442300400034 ENDBIB 32 0 1442300400035 COMMON 8 6 1442300400036 EN EN-RSL-FW ERR-5 ERR-6 ERR-7 ERR-8 1442300400037 ERR-9 ERR-10 1442300400038 MEV MEV PER-CENT PER-CENT PER-CENT PER-CENT 1442300400039 PER-CENT PER-CENT 1442300400040 8.9 0.54 0.332 0.043 0.403 2.28 1442300400041 2.2 0.2 1442300400042 ENDCOMMON 6 0 1442300400043 DATA 12 9 1442300400044 ELEMENT MASS DATA 1ERR-S 1ERR-T 1DATA 21442300400045 ERR-S 2ERR-T 2DATA 3ERR-S 3ERR-T 3DECAY-FLAG 1442300400046 NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS NO-DIM 1442300400047 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1442300400048 38.0 92.0 2.96 0.090 0.270 0.501 1442300400049 0.008 0.038 0.617 0.021 0.047 1. 1442300400050 40.0 97.0 5.36 0.170 0.340 0.909 1442300400051 0.009 0.035 1.120 0.022 0.043 2. 1442300400052 42.0 99.0 5.90 0.130 0.390 1442300400053 1.233 0.025 0.053 3. 1442300400054 44.0 105.0 5.18 0.160 0.340 0.879 1442300400055 0.010 0.035 1.083 0.022 0.044 4. 1442300400056 52.0 132.0 4.17 0.170 0.320 0.708 1442300400057 0.029 0.041 0.872 0.034 0.051 5. 1442300400058 53.0 133.0 6.40 0.210 0.440 1.086 1442300400059 0.013 0.052 1.338 0.023 0.064 6. 1442300400060 56.0 140.0 4.79 0.170 0.320 0.811 1442300400061 0.016 0.035 1.000 0.024 0.043 7. 1442300400062 58.0 143.0 3.78 0.120 0.240 0.640 1442300400063 0.015 0.026 0.789 0.021 0.032 8. 1442300400064 60.0 147.0 2.01 0.100 0.220 0.340 1442300400065 0.013 0.033 0.419 0.000 0.041 9. 1442300400066 ENDDATA 22 0 1442300400067 ENDSUBENT 66 0 1442300499999 SUBENT 14423005 20190604 14571442300500001 BIB 6 18 1442300500002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 1442300500003 (92-U-235(N,F)42-MO-99,CUM,FY)) 1442300500004 SAMPLE (92-U-235,ENR=0.9327) 1442300500005 (92-U-234,ENR=0.0105) 1442300500006 (92-U-238,ENR=0.0568) 1442300500007 Enriched 235U sample with mass 233.02 mg 1442300500008 and diameter 12.35 mm 1442300500009 DECAY-DATA Half-life of I-131=8.0252 days, assumed by compiler 1442300500010 ((2.)40-ZR-97,16.749HR,DG,743.36,0.9309) 1442300500011 ((3.)42-MO-99,65.976HR,DG,739.500,0.1226) 1442300500012 ((5.)52-TE-132,3.204D,DG,228.16,0.88) 1442300500013 ((7.)56-BA-140,12.7527D,DG,537.261,0.2439) 1442300500014 ((8.)58-CE-143,33.039HR,DG,293.266,0.428) 1442300500015 ((9.)60-ND-147,10.98D,DG,531.016,0.1337) 1442300500016 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1442300500017 HISTORY (20190604C) OG. 1442300500018 STATUS (CURVE) Fig.6 from Nucl.Dat.Sh.,119,324,2014 1442300500019 was digitized by GSYS2.4.7. 1442300500020 ENDBIB 18 0 1442300500021 COMMON 1 3 1442300500022 EN 1442300500023 MEV 1442300500024 4.6 1442300500025 ENDCOMMON 3 0 1442300500026 DATA 5 7 1442300500027 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 1442300500028 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1442300500029 40. 97. 1.0427 0.0435 2. 1442300500030 44. 105. 0.3702 0.0401 3. 1442300500031 52. 132. 1.0887 0.0535 5. 1442300500032 53. 131. 0.9117 0.0368 1442300500033 56. 140. 0.9914 0.0351 7. 1442300500034 58. 143. 0.9309 0.0318 8. 1442300500035 60. 147. 0.3504 0.0468 9. 1442300500036 ENDDATA 9 0 1442300500037 ENDSUBENT 36 0 1442300599999 SUBENT 14423006 20190604 14571442300600001 BIB 6 17 1442300600002 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 1442300600003 (92-U-238(N,F)42-MO-99,CUM,FY)) 1442300600004 SAMPLE (92-U-235,ENR=0.00026) 1442300600005 (92-U-238,ENR=0.99974) 1442300600006 Enriched 238U sample with mass 441.93 mg 1442300600007 and diameter 12.42 mm 1442300600008 DECAY-DATA Half-life of I-131=8.0252 days, assumed by compiler 1442300600009 ((2.)40-ZR-97,16.749HR,DG,743.36,0.9309) 1442300600010 ((3.)42-MO-99,65.976HR,DG,739.500,0.1226) 1442300600011 ((5.)52-TE-132,3.204D,DG,228.16,0.88) 1442300600012 ((7.)56-BA-140,12.7527D,DG,537.261,0.2439) 1442300600013 ((8.)58-CE-143,33.039HR,DG,293.266,0.428) 1442300600014 ((9.)60-ND-147,10.98D,DG,531.016,0.1337) 1442300600015 ERR-ANALYS No uncertainties in Fig.7. 1442300600016 HISTORY (20190604C) OG. 1442300600017 STATUS (CURVE) Fig.7 from Nucl.Dat.Sh.,119,324,2014 1442300600018 was digitized by GSYS2.4.7. 1442300600019 ENDBIB 17 0 1442300600020 COMMON 1 3 1442300600021 EN 1442300600022 MEV 1442300600023 4.6 1442300600024 ENDCOMMON 3 0 1442300600025 DATA 4 7 1442300600026 ELEMENT MASS DATA DECAY-FLAG 1442300600027 NO-DIM NO-DIM NO-DIM NO-DIM 1442300600028 40. 97. 0.9273 2. 1442300600029 44. 105. 0.5659 3. 1442300600030 52. 132. 0.8148 5. 1442300600031 53. 131. 0.7000 1442300600032 56. 140. 0.8080 7. 1442300600033 58. 143. 0.6886 8. 1442300600034 60. 147. 0.3670 9. 1442300600035 ENDDATA 9 0 1442300600036 ENDSUBENT 35 0 1442300699999 SUBENT 14423007 20190604 14571442300700001 BIB 6 19 1442300700002 REACTION ((94-PU-239(N,F)ELEM/MASS,CUM,FY)/ 1442300700003 (94-PU-239(N,F)42-MO-99,CUM,FY)) 1442300700004 SAMPLE (94-PU-239,ENR=0.9841) 1442300700005 (94-PU-240,ENR=0.0158) 1442300700006 (94-PU-241,ENR=0.00003) 1442300700007 (94-PU-242,ENR=0.00003) 1442300700008 Two enriched 239Pu samples with mass 233.0, 1442300700009 233.7mg and diameter 12.39, 12.40 mm, respectively 1442300700010 DECAY-DATA Half-life of I-131=8.0252 days, assumed by compiler 1442300700011 ((2.)40-ZR-97,16.749HR,DG,743.36,0.9309) 1442300700012 ((5.)52-TE-132,3.204D,DG,228.16,0.88) 1442300700013 ((7.)56-BA-140,12.7527D,DG,537.261,0.2439) 1442300700014 ((8.)58-CE-143,33.039HR,DG,293.266,0.428) 1442300700015 ((9.)60-ND-147,10.98D,DG,531.016,0.1337) 1442300700016 (42-MO-99,65.976HR,DG,739.500,0.1226) 1442300700017 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1442300700018 HISTORY (20190604C) OG. 1442300700019 STATUS (CURVE) Fig.8 from Nucl.Dat.Sh.,119,324,2014 1442300700020 was digitized by GSYS2.4.7. 1442300700021 ENDBIB 19 0 1442300700022 COMMON 1 3 1442300700023 EN 1442300700024 MEV 1442300700025 4.6 1442300700026 ENDCOMMON 3 0 1442300700027 DATA 5 6 1442300700028 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 1442300700029 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1442300700030 40. 97. 0.9615 0.0314 2. 1442300700031 52. 132. 1.1806 0.0597 5. 1442300700032 53. 131. 0.8303 0.0424 1442300700033 56. 140. 0.8701 0.0408 7. 1442300700034 58. 143. 0.6318 0.0251 8. 1442300700035 60. 147. 0.3715 0.0204 9. 1442300700036 ENDDATA 8 0 1442300700037 ENDSUBENT 36 0 1442300799999 ENDENTRY 7 0 1442399999999