ENTRY 14316 20160608 14181431600000001 SUBENT 14316001 20160608 14181431600100001 BIB 9 41 1431600100002 TITLE Utilizing (p,d) and (p,t) reactions to obtain (n,f) 1431600100003 cross sections in uranium nuclei via the 1431600100004 surrogate-ratio method 1431600100005 AUTHOR (R.O.Hughes,C.W.Beausang,T.J.Ross,J.T.Burke, 1431600100006 N.D.Scielzo,M.S.Basunia,C.M.Campbell,R.J.Casperson, 1431600100007 H.L.Crawford,J.E.Escher,J.Munson,L.W.Phair,J.J.Ressler)1431600100008 INSTITUTE (1USALRL,1USABRK,2UK SUR) 1431600100009 (1USAUSA)University of Richmond,Richmond,Virginia 1431600100010 REFERENCE (J,PR/C,85,024613,2012) 1431600100011 FACILITY (CYCLO,1USABRK) Experiment performed using the 88 inch 1431600100012 cyclotron at Lawrence Berkeley National Laboratory 1431600100013 DETECTOR (TELES,SI,SI) The Silicon Telescope Array for 1431600100014 Reaction Studies (STARS) was used to measure outgoing 1431600100015 deuterons and tritons over an angular range of 34deg 1431600100016 to 64deg. For this experiment STARS consisted of one 1431600100017 140 mu-m dE and two 1000 mu-m E1 and E2 silicon 1431600100018 detectors of Micron S2 type. Coincident fission 1431600100019 fragments were measured at backward angles between 1431600100020 109deg and 137deg using a second 140 mu-m Micron S2 1431600100021 type detector. Each S2 detector was segmented into 1431600100022 48 rings on one side and 16 sectors on the other. 1431600100023 For the present experiment the rings and sectors were 1431600100024 bussed together so each detector had 8 sectors and 24 1431600100025 one-millimeter rings to measure incident charged 1431600100026 particles. 1431600100027 (HPGE) The STARS chamber was surrounded by six clover 1431600100028 g-ray detectors from the Livermore-Berkeley Array 1431600100029 for Collaborative Experiments (LIBERACE), allowing 1431600100030 for both particle-fission and particle-gamma 1431600100031 coincidence events to be collected. 1431600100032 METHOD (EDE) E-dE method was used to identify deuterons 1431600100033 and tritons 1431600100034 (COINC) Coincidence between STARS silicon array and 1431600100035 LIBERACE gamma detector array was required to measure 1431600100036 gamma rays in coincidence with fission fragments and 1431600100037 emitted charged particles. Single particles events, 1431600100038 particle-gamma and particle-fission coincidence events 1431600100039 were collected. 1431600100040 MONITOR (92-U-235(N,F),,SIG) 1431600100041 HISTORY (20120301C) Compiled by S.H. 1431600100042 (20160608A) OS. REACTIONs corrected in subs.2-5 1431600100043 ENDBIB 41 0 1431600100044 NOCOMMON 0 0 1431600100045 ENDSUBENT 44 0 1431600199999 SUBENT 14316002 20160608 14181431600200001 BIB 6 16 1431600200002 REACTION ((92-U-236(N,F),,SIG,,,DERIV)/ 1431600200003 (92-U-234(N,F),,SIG,,,DERIV)) 1431600200004 SAMPLE (92-U-236,ENR=0.8023) 236U target was prepared by 1431600200005 electrodepositing isotopically enriched 236U on 100 1431600200006 mu-g/cm2 carbon foil. Thickness of the target was 1431600200007 322+-18 mu-g/cm2 1431600200008 (92-U-238,ENR=0.9923) Self-supporting metallic foil 1431600200009 with thickness of 1450+-90 mu-g/cm2 1431600200010 ANALYSIS (SURGT) Fission cross section ratios 1431600200011 236U(n,f)/234U(n,f) was determined using the surrogate 1431600200012 ratio method from 238U(p,df)/236U(p,df) cross 1431600200013 section ratios. 1431600200014 ERR-ANALYS (DATA-ERR) No information given 1431600200015 STATUS (CURVE) Data taken from fig.5a of the reference, 1431600200016 waiting for data from author. 1431600200017 HISTORY (20160608A) Added DERIV to SF9 1431600200018 ENDBIB 16 0 1431600200019 NOCOMMON 0 0 1431600200020 DATA 3 94 1431600200021 EN DATA DATA-ERR 1431600200022 MEV NO-DIM NO-DIM 1431600200023 0.2 0.15 0.02 1431600200024 0.3 0.07 0.01 1431600200025 0.4 0.06 0.01 1431600200026 0.5 0.07 0.01 1431600200027 0.6 0.08 0.01 1431600200028 0.7 0.12 0.01 1431600200029 0.8 0.20 0.01 1431600200030 0.9 0.28 0.02 1431600200031 1.0 0.37 0.03 1431600200032 1.1 0.44 0.03 1431600200033 1.2 0.50 0.04 1431600200034 1.3 0.54 0.04 1431600200035 1.4 0.58 0.04 1431600200036 1.5 0.55 0.04 1431600200037 1.6 0.56 0.04 1431600200038 1.7 0.55 0.04 1431600200039 1.8 0.53 0.04 1431600200040 1.9 0.54 0.04 1431600200041 2.0 0.59 0.04 1431600200042 2.1 0.59 0.04 1431600200043 2.2 0.63 0.04 1431600200044 2.3 0.62 0.05 1431600200045 2.4 0.63 0.05 1431600200046 2.5 0.64 0.05 1431600200047 2.6 0.60 0.04 1431600200048 2.7 0.62 0.04 1431600200049 2.8 0.60 0.04 1431600200050 2.9 0.65 0.05 1431600200051 3.0 0.63 0.05 1431600200052 3.1 0.62 0.05 1431600200053 3.2 0.62 0.04 1431600200054 3.3 0.63 0.05 1431600200055 3.4 0.63 0.04 1431600200056 3.5 0.62 0.04 1431600200057 3.6 0.64 0.05 1431600200058 3.7 0.65 0.04 1431600200059 3.8 0.62 0.04 1431600200060 3.9 0.67 0.05 1431600200061 4.0 0.66 0.05 1431600200062 4.1 0.65 0.05 1431600200063 4.2 0.63 0.05 1431600200064 4.3 0.65 0.05 1431600200065 4.4 0.66 0.05 1431600200066 4.5 0.69 0.05 1431600200067 4.6 0.69 0.05 1431600200068 4.7 0.67 0.05 1431600200069 4.8 0.73 0.05 1431600200070 4.9 0.75 0.06 1431600200071 5.0 0.63 0.05 1431600200072 5.1 0.67 0.05 1431600200073 5.2 0.69 0.05 1431600200074 5.3 0.69 0.05 1431600200075 5.4 0.67 0.05 1431600200076 5.5 0.73 0.05 1431600200077 5.6 0.69 0.05 1431600200078 5.7 0.73 0.05 1431600200079 5.8 0.74 0.05 1431600200080 5.9 0.70 0.05 1431600200081 6.0 0.72 0.05 1431600200082 6.1 0.75 0.05 1431600200083 6.2 0.73 0.05 1431600200084 6.3 0.77 0.06 1431600200085 6.4 0.75 0.05 1431600200086 6.5 0.81 0.06 1431600200087 6.6 0.79 0.06 1431600200088 6.7 0.83 0.06 1431600200089 6.8 0.82 0.06 1431600200090 6.9 0.77 0.05 1431600200091 7.0 0.86 0.06 1431600200092 7.1 0.82 0.06 1431600200093 7.2 0.81 0.06 1431600200094 7.3 0.91 0.07 1431600200095 7.4 0.90 0.06 1431600200096 7.5 0.94 0.07 1431600200097 7.6 0.81 0.06 1431600200098 7.7 0.80 0.06 1431600200099 7.8 0.80 0.06 1431600200100 7.9 0.80 0.06 1431600200101 8.0 0.87 0.07 1431600200102 8.1 1.04 0.08 1431600200103 8.2 0.95 0.07 1431600200104 8.3 0.89 0.07 1431600200105 8.4 0.87 0.07 1431600200106 8.5 1.07 0.08 1431600200107 8.6 0.93 0.07 1431600200108 8.7 0.98 0.08 1431600200109 8.8 0.98 0.08 1431600200110 8.9 0.97 0.08 1431600200111 9.0 0.94 0.07 1431600200112 9.1 0.84 0.07 1431600200113 9.2 0.90 0.07 1431600200114 9.3 0.98 0.08 1431600200115 9.4 1.01 0.09 1431600200116 9.5 0.85 0.08 1431600200117 ENDDATA 96 0 1431600200118 ENDSUBENT 117 0 1431600299999 SUBENT 14316003 20160608 14181431600300001 BIB 7 15 1431600300002 REACTION (92-U-236(N,F),,SIG,,,DERIV) 1431600300003 ANALYSIS (SURGT) Fission cross section of 236U was determined 1431600300004 using the surrogate ratio method. The (n,f) cross 1431600300005 section was deduced from cross section ratios 1431600300006 236U(n,f)/234U(n,f). Cross section of 236U(n,f) 1431600300007 reaction was determined from 236U(n,f)/234U(n,f) 1431600300008 ratio and 234U(n,f) cross section. 1431600300009 MONITOR (92-U-234(N,F),,SIG) 1431600300010 MONIT-REF (,,3,ENDF/B-VII.0,,2006) 1431600300011 ERR-ANALYS (DATA-ERR) No information given 1431600300012 STATUS (CURVE) Data taken from fig.5b of the reference, 1431600300013 waiting for data from author. 1431600300014 (DEP,14316002) Cross section was determined from ratio 1431600300015 measured in 14316002 1431600300016 HISTORY (20160608A) Added DERIV to SF9 1431600300017 ENDBIB 15 0 1431600300018 NOCOMMON 0 0 1431600300019 DATA 3 97 1431600300020 EN DATA DATA-ERR 1431600300021 MEV B B 1431600300022 0.1 0.003 1431600300023 0.2 0.007 1431600300024 0.3 0.009 1431600300025 0.4 0.014 1431600300026 0.5 0.031 1431600300027 0.6 0.058 1431600300028 0.7 0.122 0.011 1431600300029 0.8 0.249 0.019 1431600300030 0.9 0.318 0.021 1431600300031 1.0 0.411 0.030 1431600300032 1.1 0.511 0.036 1431600300033 1.2 0.600 0.044 1431600300034 1.3 0.676 0.047 1431600300035 1.4 0.744 0.053 1431600300036 1.5 0.731 0.051 1431600300037 1.6 0.777 0.051 1431600300038 1.7 0.813 0.059 1431600300039 1.8 0.809 0.057 1431600300040 1.9 0.835 0.057 1431600300041 2.0 0.900 0.065 1431600300042 2.1 0.886 0.066 1431600300043 2.2 0.940 0.068 1431600300044 2.3 0.919 0.065 1431600300045 2.4 0.936 0.068 1431600300046 2.5 0.945 0.066 1431600300047 2.6 0.896 0.065 1431600300048 2.7 0.926 0.065 1431600300049 2.8 0.888 0.061 1431600300050 2.9 0.962 0.063 1431600300051 3.0 0.949 0.068 1431600300052 3.1 0.926 0.066 1431600300053 3.2 0.926 0.066 1431600300054 3.3 0.949 0.068 1431600300055 3.4 0.945 0.068 1431600300056 3.5 0.918 0.065 1431600300057 3.6 0.947 0.065 1431600300058 3.7 0.948 0.066 1431600300059 3.8 0.895 0.065 1431600300060 3.9 0.971 0.068 1431600300061 4.0 0.950 0.066 1431600300062 4.1 0.918 0.066 1431600300063 4.2 0.899 0.066 1431600300064 4.3 0.912 0.070 1431600300065 4.4 0.924 0.066 1431600300066 4.5 0.971 0.070 1431600300067 4.7 0.956 0.070 1431600300068 4.7 0.923 0.065 1431600300069 4.9 0.999 0.074 1431600300070 5.0 1.016 0.072 1431600300071 5.1 0.844 0.063 1431600300072 5.2 0.897 0.065 1431600300073 5.3 0.910 0.065 1431600300074 5.4 0.904 0.063 1431600300075 5.5 0.866 0.063 1431600300076 5.6 0.938 0.068 1431600300077 5.7 0.878 0.063 1431600300078 5.8 0.919 0.065 1431600300079 5.9 0.942 0.072 1431600300080 6.0 0.893 0.070 1431600300081 6.1 0.917 0.065 1431600300082 6.2 0.965 0.072 1431600300083 6.3 0.970 0.070 1431600300084 6.4 1.054 0.076 1431600300085 6.5 1.054 0.080 1431600300086 6.6 1.177 0.084 1431600300087 6.7 1.175 0.085 1431600300088 6.8 1.270 0.093 1431600300089 6.9 1.289 0.093 1431600300090 7.0 1.258 0.093 1431600300091 7.1 1.435 0.102 1431600300092 7.2 1.418 0.101 1431600300093 7.3 1.435 0.104 1431600300094 7.4 1.664 0.121 1431600300095 7.5 1.685 0.120 1431600300096 7.6 1.793 0.129 1431600300097 7.7 1.594 0.116 1431600300098 7.8 1.604 0.120 1431600300099 7.9 1.638 0.118 1431600300100 8.0 1.658 0.123 1431600300101 8.1 1.837 0.137 1431600300102 8.2 2.211 0.163 1431600300103 8.3 2.028 0.154 1431600300104 8.4 1.922 0.148 1431600300105 8.5 1.888 0.142 1431600300106 8.6 2.317 0.178 1431600300107 8.7 2.009 0.148 1431600300108 8.8 2.127 0.169 1431600300109 8.9 2.127 0.163 1431600300110 9.0 2.091 0.165 1431600300111 9.1 2.026 0.163 1431600300112 9.2 1.823 0.148 1431600300113 9.3 1.937 0.163 1431600300114 9.4 2.119 0.178 1431600300115 9.5 2.178 0.188 1431600300116 9.6 1.832 0.161 1431600300117 9.7 1.817 0.159 1431600300118 9.8 2.417 0.222 1431600300119 ENDDATA 99 0 1431600300120 ENDSUBENT 119 0 1431600399999 SUBENT 14316004 20160608 14181431600400001 BIB 6 16 1431600400002 REACTION ((92-U-235(N,F),,SIG,,,DERIV)/ 1431600400003 (92-U-233(N,F),,SIG,,,DERIV)) 1431600400004 SAMPLE (92-U-236,ENR=0.8023) 236U target was prepared by 1431600400005 electrodepositing isotopically enriched 236U on 100 1431600400006 mu-g/cm2 carbon foil. Thickness of the target was 1431600400007 322+-18 mu-g/cm2 1431600400008 (92-U-238,ENR=0.9923) Self-supporting metallic foil 1431600400009 with thickness of 1450+-90 mu-g/cm2 1431600400010 ANALYSIS (SURGT) Fission cross section ratios 1431600400011 235U(n,f)/233U(n,f) was determined using the surrogate 1431600400012 ratio method from 238U(p,tf)/236U(p,tf) cross 1431600400013 section ratios. 1431600400014 ERR-ANALYS (DATA-ERR) No information given 1431600400015 STATUS (CURVE) Data taken from fig.7a of the reference, 1431600400016 waiting for data from author. 1431600400017 HISTORY (20160608A) Added DERIV to SF9 1431600400018 ENDBIB 16 0 1431600400019 NOCOMMON 0 0 1431600400020 DATA 3 77 1431600400021 EN DATA DATA-ERR 1431600400022 MEV NO-DIM NO-DIM 1431600400023 0.0 7.66E-01 5.62E-02 1431600400024 0.1 6.97E-01 5.31E-02 1431600400025 0.2 6.60E-01 4.80E-02 1431600400026 0.3 6.59E-01 4.90E-02 1431600400027 0.4 6.36E-01 4.50E-02 1431600400028 0.5 6.43E-01 4.29E-02 1431600400029 0.6 6.33E-01 4.50E-02 1431600400030 0.7 6.43E-01 4.19E-02 1431600400031 0.8 6.51E-01 4.50E-02 1431600400032 0.9 6.65E-01 5.01E-02 1431600400033 1.0 6.77E-01 4.80E-02 1431600400034 1.1 6.46E-01 4.90E-02 1431600400035 1.2 6.79E-01 4.80E-02 1431600400036 1.3 6.69E-01 4.90E-02 1431600400037 1.4 6.77E-01 4.80E-02 1431600400038 1.5 6.54E-01 4.80E-02 1431600400039 1.6 6.46E-01 4.60E-02 1431600400040 1.7 6.58E-01 4.80E-02 1431600400041 1.8 6.72E-01 4.60E-02 1431600400042 1.9 6.80E-01 5.42E-02 1431600400043 2.0 6.75E-01 4.70E-02 1431600400044 2.1 6.22E-01 4.80E-02 1431600400045 2.2 6.54E-01 4.80E-02 1431600400046 2.3 6.67E-01 5.11E-02 1431600400047 2.4 6.69E-01 5.01E-02 1431600400048 2.5 6.69E-01 5.42E-02 1431600400049 2.6 6.74E-01 5.01E-02 1431600400050 2.7 6.71E-01 4.90E-02 1431600400051 2.8 6.84E-01 4.90E-02 1431600400052 2.9 6.85E-01 5.01E-02 1431600400053 3.0 7.36E-01 5.01E-02 1431600400054 3.1 6.65E-01 4.90E-02 1431600400055 3.2 7.17E-01 5.01E-02 1431600400056 3.3 7.08E-01 5.01E-02 1431600400057 3.4 6.91E-01 5.11E-02 1431600400058 3.5 6.81E-01 5.11E-02 1431600400059 3.6 6.70E-01 5.01E-02 1431600400060 3.7 7.72E-01 5.93E-02 1431600400061 3.8 7.02E-01 5.11E-02 1431600400062 3.9 7.70E-01 5.72E-02 1431600400063 4.0 7.31E-01 5.52E-02 1431600400064 4.1 7.52E-01 5.72E-02 1431600400065 4.2 7.03E-01 5.52E-02 1431600400066 4.3 7.63E-01 5.72E-02 1431600400067 4.4 6.74E-01 5.41E-02 1431600400068 4.5 7.17E-01 5.62E-02 1431600400069 4.6 7.42E-01 5.93E-02 1431600400070 4.7 6.98E-01 5.62E-02 1431600400071 4.8 7.41E-01 6.03E-02 1431600400072 4.9 7.63E-01 6.13E-02 1431600400073 5.0 7.54E-01 6.03E-02 1431600400074 5.1 7.93E-01 6.54E-02 1431600400075 5.2 7.31E-01 6.13E-02 1431600400076 5.3 8.37E-01 6.34E-02 1431600400077 5.4 8.38E-01 6.54E-02 1431600400078 5.5 8.50E-01 7.15E-02 1431600400079 5.6 8.53E-01 6.84E-02 1431600400080 5.7 8.48E-01 6.54E-02 1431600400081 5.8 9.08E-01 7.05E-02 1431600400082 5.9 8.64E-01 6.95E-02 1431600400083 6.0 9.34E-01 7.46E-02 1431600400084 6.1 9.87E-01 7.77E-02 1431600400085 6.2 1.02E+00 7.46E-02 1431600400086 6.3 1.06E+00 8.38E-02 1431600400087 6.4 9.96E-01 7.97E-02 1431600400088 6.5 1.21E+00 9.60E-02 1431600400089 6.6 1.22E+00 8.79E-02 1431600400090 6.7 1.25E+00 9.81E-02 1431600400091 6.8 1.14E+00 8.99E-02 1431600400092 6.9 1.32E+00 1.01E-01 1431600400093 7.0 1.19E+00 8.99E-02 1431600400094 7.1 1.49E+00 1.13E-01 1431600400095 7.2 1.64E+00 1.24E-01 1431600400096 7.3 1.28E+00 1.01E-01 1431600400097 7.4 1.64E+00 1.33E-01 1431600400098 7.5 1.59E+00 1.47E-01 1431600400099 7.6 1.52E+00 1.30E-01 1431600400100 ENDDATA 79 0 1431600400101 ENDSUBENT 100 0 1431600499999 SUBENT 14316005 20160608 14181431600500001 BIB 7 15 1431600500002 REACTION (92-U-235(N,F),,SIG,,,DERIV) 1431600500003 ANALYSIS (SURGT) Fission cross section of 235U was determined 1431600500004 using the surrogate ratio method. The (n,f) cross 1431600500005 section was deduced from cross section ratios 1431600500006 235U(n,f)/233U(n,f). Cross section of 235U(n,f) 1431600500007 reaction was determined from 235U(n,f)/233U(n,f) 1431600500008 ratio and 233U(n,f) cross section. 1431600500009 MONITOR (92-U-233(N,F),,SIG) 1431600500010 MONIT-REF (,,3,ENDF/B-VII.0,,2006) 1431600500011 ERR-ANALYS (DATA-ERR) No information given 1431600500012 STATUS (CURVE) Data taken from fig.7b of the reference, 1431600500013 waiting for data from author. 1431600500014 (DEP,14316004) Cross section was determined from ratio 1431600500015 measured in 14316004 1431600500016 HISTORY (20160608A) Added DERIV to SF9 1431600500017 ENDBIB 15 0 1431600500018 NOCOMMON 0 0 1431600500019 DATA 3 71 1431600500020 EN DATA DATA-ERR 1431600500021 MEV B B 1431600500022 0.0 2.70E+00 1.89E-01 1431600500023 0.1 1.55E+00 1.04E-01 1431600500024 0.2 1.40E+00 9.38E-02 1431600500025 0.3 1.40E+00 9.73E-02 1431600500026 0.4 1.29E+00 9.02E-02 1431600500027 0.5 1.25E+00 8.85E-02 1431600500028 0.6 1.20E+00 7.96E-02 1431600500029 0.7 1.20E+00 8.49E-02 1431600500030 0.8 1.20E+00 7.96E-02 1431600500031 0.9 1.21E+00 7.96E-02 1431600500032 1.0 1.24E+00 8.67E-02 1431600500033 1.1 1.18E+00 8.14E-02 1431600500034 1.2 1.25E+00 9.38E-02 1431600500035 1.3 1.24E+00 8.14E-02 1431600500036 1.4 1.26E+00 8.85E-02 1431600500037 1.5 1.23E+00 8.49E-02 1431600500038 1.6 1.23E+00 8.67E-02 1431600500039 1.7 1.26E+00 8.14E-02 1431600500040 1.8 1.29E+00 9.20E-02 1431600500041 1.9 1.31E+00 9.20E-02 1431600500042 2.0 1.31E+00 9.20E-02 1431600500043 2.1 1.21E+00 8.14E-02 1431600500044 2.2 1.28E+00 9.02E-02 1431600500045 2.3 1.30E+00 9.02E-02 1431600500046 2.4 1.29E+00 8.67E-02 1431600500047 2.5 1.28E+00 8.14E-02 1431600500048 2.6 1.28E+00 8.67E-02 1431600500049 2.7 1.27E+00 9.02E-02 1431600500050 2.8 1.29E+00 9.20E-02 1431600500051 2.9 1.28E+00 8.67E-02 1431600500052 3.0 1.36E+00 9.91E-02 1431600500053 3.1 1.22E+00 8.49E-02 1431600500054 3.2 1.31E+00 9.02E-02 1431600500055 3.3 1.28E+00 9.20E-02 1431600500056 3.4 1.24E+00 7.78E-02 1431600500057 3.5 1.21E+00 7.96E-02 1431600500058 3.6 1.18E+00 8.14E-02 1431600500059 3.7 1.35E+00 9.91E-02 1431600500060 3.8 1.22E+00 8.14E-02 1431600500061 3.9 1.32E+00 9.38E-02 1431600500062 4.0 1.25E+00 8.67E-02 1431600500063 4.1 1.27E+00 8.49E-02 1431600500064 4.2 1.18E+00 8.14E-02 1431600500065 4.3 1.27E+00 8.49E-02 1431600500066 4.4 1.12E+00 6.90E-02 1431600500067 4.5 1.18E+00 7.78E-02 1431600500068 4.6 1.21E+00 7.43E-02 1431600500069 4.7 1.13E+00 7.61E-02 1431600500070 4.8 1.19E+00 7.61E-02 1431600500071 4.9 1.21E+00 7.96E-02 1431600500072 5.0 1.19E+00 7.61E-02 1431600500073 5.1 1.25E+00 7.96E-02 1431600500074 5.2 1.14E+00 7.61E-02 1431600500075 5.3 1.30E+00 9.55E-02 1431600500076 5.4 1.29E+00 9.02E-02 1431600500077 5.5 1.31E+00 8.85E-02 1431600500078 5.6 1.30E+00 8.14E-02 1431600500079 5.7 1.30E+00 9.02E-02 1431600500080 5.8 1.40E+00 9.73E-02 1431600500081 5.9 1.35E+00 9.38E-02 1431600500082 6.0 1.47E+00 1.01E-01 1431600500083 6.1 1.60E+00 1.11E-01 1431600500084 6.2 1.71E+00 1.27E-01 1431600500085 6.3 1.83E+00 1.29E-01 1431600500086 6.4 1.77E+00 1.20E-01 1431600500087 6.5 2.21E+00 1.57E-01 1431600500088 6.6 2.29E+00 1.77E-01 1431600500089 6.7 2.41E+00 1.68E-01 1431600500090 6.8 2.23E+00 1.52E-01 1431600500091 6.9 2.62E+00 1.96E-01 1431600500092 7.0 2.39E+00 1.73E-01 1431600500093 ENDDATA 73 0 1431600500094 ENDSUBENT 93 0 1431600599999 ENDENTRY 5 0 1431699999999