ENTRY 14259 20160804 14211425900000001 SUBENT 14259001 20160804 14211425900100001 BIB 9 24 1425900100002 TITLE Fission fragment mass and energy distributions as a 1425900100003 function of incident neutron energy measured in a 1425900100004 lead slowing-down spectrometer 1425900100005 AUTHOR (C.Romano,Y.Danon,R.Block,J.Thompson,E.Blain,E.Bond) 1425900100006 INSTITUTE (1USARPI,1USALAS) 1425900100007 REFERENCE (J,PR/C,81,014607,2010) Main reference 1425900100008 (C,2007NICE,1,371,2007) Preliminary data 1425900100009 INC-SPECT The incident neutron spectrum is characterized by the 1425900100010 following formula: 1425900100011 (dEn/En)FWHM=[0.0835+(0.128/En)+3.05E-05*En]**(1/2) 1425900100012 DETECTOR (FISCH) Double sided fission chamber with Frisch grid 1425900100013 placed in the lead slowing down spectrometer (LSDS). 1425900100014 LSDS consisted of cube of lead with mass of 75 ton 1425900100015 and side of 1.8 m. Lead was covered with a 0.75-mm 1425900100016 layer of cadmium to prevent neutrons that have escaped 1425900100017 and thermalized from re-entering the lead. 1425900100018 METHOD (SLODT,PLSED) 1425900100019 STATUS (APRVD) Approved by author C.R. by mail 12. 3. 2010 1425900100020 HISTORY (20100128C) Compiled by S.H. 1425900100021 (20100617A) Added Method code, modified reaction 1425900100022 in subentry 4 1425900100023 (20120816U) SD: FACILITY, SAMPLE and INC-SOURCE moved 1425900100024 to Subents 2-7.1425900100025 (20160801U) Minor typogr.corr. in sub.1. 1425900100026 ENDBIB 24 0 1425900100027 NOCOMMON 0 0 1425900100028 ENDSUBENT 27 0 1425900199999 SUBENT 14259002 20120816 13851425900200001 BIB 6 23 1425900200002 REACTION (92-U-235(N,F),,SIG,,SPA) 1425900200003 FACILITY (LINAC,1USARPI) Experiment performed at RPI 60-MeV 1425900200004 electron Linac. 1425900200005 SAMPLE The 235U sample was made at Los Alamos National Labs 1425900200006 and was prepared by dissolving 99.98% 235U in 8M HNO3. 1425900200007 The solution was dried down and redissolved in absolute1425900200008 alcohol and 25.3+-0.5 mu-g was deposited in an area of 1425900200009 1 cm diameter on a polyimide film. The sample was 1425900200010 placed on cathode in the middle of the fission chamber 1425900200011 INC-SOURCE (PHOTO)Neutrons were produced through a (gamma,n) 1425900200012 reaction when electrons from the RPI 60-MeV electron 1425900200013 linac interact with a tantalum target, placed in the 1425900200014 center of lead slowing down spectrometer.The linac was 1425900200015 run at an average electron current of 8 mu-A, 1425900200016 delivering 58-MeV electrons in a pulse width of 200 ns 1425900200017 at 180 Hz.The neutron energy and flux are experimentaly1425900200018 known functions of slowing down time and electron beam 1425900200019 intensity. The neutron-energy resolution (FWHM)] in 1425900200020 the energy range of 0.1 eV to 1 keV was 1425900200021 approximately 35%. 1425900200022 STATUS (TABLE) Data presented in fig. 5 of the PR/C,81,014607 1425900200023 reference sent by author (C.R.) 1425900200024 ERR-ANALYS (ERR-S) Statistical uncertainty 1425900200025 ENDBIB 23 0 1425900200026 NOCOMMON 0 0 1425900200027 DATA 3 144 1425900200028 EN DATA ERR-S 1425900200029 EV B B 1425900200030 0.112 209.11 1425900200031 0.137 193.67 1425900200032 0.164 182.92 1425900200033 0.195 172.28 1425900200034 0.229 163.38 1425900200035 0.265 150.08 1425900200036 0.305 139.88 1425900200037 0.348 122.36 1425900200038 0.395 111.76 1425900200039 0.445 98.07 1425900200040 0.499 87.95 1425900200041 0.557 82.02 1425900200042 0.619 74.17 1425900200043 0.684 70.12 1425900200044 0.755 69.04 1425900200045 0.830 66.88 1425900200046 0.910 63.35 1425900200047 0.994 58.88 1425900200048 1.085 55.21 7.58 1425900200049 1.180 48.09 1425900200050 1.282 41.86 1425900200051 1.389 37.86 1425900200052 1.502 31.55 1425900200053 1.624 29.27 1425900200054 1.751 27.41 1425900200055 1.885 25.49 1425900200056 2.029 25.48 1425900200057 2.180 23.54 1425900200058 2.340 23.16 4.46 1425900200059 2.509 24.16 1425900200060 2.689 23.45 1425900200061 2.875 23.94 1425900200062 3.071 22.79 1425900200063 3.282 24.18 4.43 1425900200064 3.503 20.23 1425900200065 3.740 18.65 1425900200066 3.987 18.18 1425900200067 4.242 17.10 3.64 1425900200068 4.523 17.32 1425900200069 4.822 18.52 1425900200070 5.130 20.47 1425900200071 5.443 22.39 1425900200072 5.787 26.48 1425900200073 6.149 29.52 1425900200074 6.530 34.77 1425900200075 6.931 38.28 1425900200076 7.350 44.93 1425900200077 7.809 48.94 1425900200078 8.266 51.04 6.06 1425900200079 8.765 50.91 1425900200080 9.310 48.31 1425900200081 9.849 44.02 1425900200082 10.403 43.25 1425900200083 11.005 41.59 1425900200084 11.662 40.07 1425900200085 12.379 39.67 1425900200086 13.118 39.01 1425900200087 13.876 39.44 4.85 1425900200088 14.649 37.97 1425900200089 15.487 39.63 1425900200090 16.400 41.15 1425900200091 17.326 43.84 1425900200092 18.334 44.51 1425900200093 19.431 44.22 4.82 1425900200094 20.542 43.54 1425900200095 21.653 40.58 1425900200096 22.857 38.87 1425900200097 24.165 38.49 1425900200098 25.587 36.33 4.24 1425900200099 27.005 37.33 1425900200100 28.544 37.96 1425900200101 30.218 38.54 1425900200102 31.871 39.37 1425900200103 33.664 40.68 4.43 1425900200104 35.612 38.93 1425900200105 37.514 39.83 1425900200106 39.573 37.88 1425900200107 41.805 37.16 1425900200108 44.232 37.35 1425900200109 46.877 36.90 1425900200110 49.432 37.40 4.11 1425900200111 52.201 35.84 1425900200112 54.820 35.16 1425900200113 57.641 32.34 1425900200114 61.141 31.00 1425900200115 64.471 28.05 1425900200116 68.080 26.67 1425900200117 72.002 25.90 1425900200118 75.639 25.00 1425900200119 80.242 24.78 1425900200120 85.279 23.63 1425900200121 89.983 22.49 1425900200122 95.088 21.90 1425900200123 99.680 20.77 3.33 1425900200124 104.614 21.32 1425900200125 111.034 20.71 1425900200126 116.847 20.23 1425900200127 123.128 20.79 2.52 1425900200128 131.357 20.62 1425900200129 138.861 20.12 1425900200130 145.338 19.15 1425900200131 154.091 18.98 1425900200132 163.660 18.91 1425900200133 171.972 18.06 1425900200134 180.933 18.01 1425900200135 190.613 18.35 1425900200136 201.092 17.87 1425900200137 212.459 18.38 2.37 1425900200138 224.817 17.64 1425900200139 238.287 17.01 1425900200140 253.004 17.14 1425900200141 269.127 16.37 1425900200142 282.254 16.16 1425900200143 296.364 14.55 1425900200144 316.885 13.70 1425900200145 333.708 13.28 1425900200146 351.907 13.07 1425900200147 371.637 12.64 1425900200148 393.073 12.09 1425900200149 416.419 12.75 2.19 1425900200150 441.908 12.13 1425900200151 469.811 11.89 1425900200152 489.908 12.42 2.04 1425900200153 522.560 11.95 1425900200154 558.588 11.55 1425900200155 584.717 11.68 1425900200156 612.724 11.35 1425900200157 642.792 10.63 1425900200158 692.219 10.01 1425900200159 747.576 9.68 1425900200160 788.253 9.26 1425900200161 832.342 8.69 1425900200162 880.237 8.46 1425900200163 932.389 8.26 1425900200164 989.315 7.82 1425900200165 1051.619 7.58 1425900200166 1120.000 7.46 1425900200167 1195.274 7.26 1425900200168 1278.399 6.91 1425900200169 1370.507 6.73 1425900200170 1472.940 6.45 1425900200171 1587.302 6.31 1425900200172 1715.518 6.10 1425900200173 1859.921 4.94 1425900200174 ENDDATA 146 0 1425900200175 ENDSUBENT 174 0 1425900299999 SUBENT 14259003 20120816 13851425900300001 BIB 7 25 1425900300002 REACTION (92-U-235(N,F)MASS,PRE,FY,,SPA) 1425900300003 FACILITY (LINAC,1USARPI) Experiment performed at RPI 60-MeV 1425900300004 electron Linac. 1425900300005 SAMPLE The 235U sample was made at Los Alamos National Labs 1425900300006 and was prepared by dissolving 99.98% 235U in 8M HNO3. 1425900300007 The solution was dried down and redissolved in absolute1425900300008 alcohol and 25.3+-0.5 mu-g was deposited in an area of 1425900300009 1 cm diameter on a polyimide film. The sample was 1425900300010 placed on cathode in the middle of the fission chamber 1425900300011 INC-SOURCE (PHOTO)Neutrons were produced through a (gamma,n) 1425900300012 reaction when electrons from the RPI 60-MeV electron 1425900300013 Linac interact with a tantalum target, placed in the 1425900300014 center of lead slowing down spectrometer.The Linac was 1425900300015 run at an average electron current of 8 mu-A, 1425900300016 delivering 58-MeV electrons in a pulse width of 200 ns 1425900300017 at 180 Hz.The neutron energy and flux are experimentaly1425900300018 known functions of slowing down time and electron beam 1425900300019 intensity. The neutron-energy resolution (FWHM)] in 1425900300020 the energy range of 0.1 eV to 1 keV was 1425900300021 approximately 35%. 1425900300022 STATUS (TABLE) Data presented in bottom part of fig.6 1425900300023 of the PR/C,81,014607 reference sent by author (C.R.) 1425900300024 Mass calculated from half-integers by compiler 1425900300025 ERR-ANALYS (ERR-S) Statistical uncertainty 1425900300026 HISTORY (20120816A) SD: SF8=MXW -> SPA 1425900300027 ENDBIB 25 0 1425900300028 COMMON 1 3 1425900300029 EN-MAX 1425900300030 EV 1425900300031 0.1 1425900300032 ENDCOMMON 3 0 1425900300033 DATA 3 100 1425900300034 MASS DATA ERR-S 1425900300035 NO-DIM PRD/FIS PRD/FIS 1425900300036 65.0 6.77E-05 1425900300037 68.0 1.35E-04 1425900300038 71.0 6.77E-05 8.83E-05 1425900300039 72.0 1.35E-04 1.53E-04 1425900300040 73.0 6.77E-05 1425900300041 74.0 6.77E-05 1.25E-04 1425900300042 75.0 4.74E-04 1.77E-04 1425900300043 76.0 2.03E-04 2.79E-04 1425900300044 77.0 2.03E-04 3.42E-04 1425900300045 78.0 5.42E-04 4.24E-04 1425900300046 79.0 6.10E-04 4.59E-04 1425900300047 80.0 7.45E-04 4.76E-04 1425900300048 81.0 1.76E-03 6.67E-04 1425900300049 82.0 2.57E-03 8.09E-04 1425900300050 83.0 3.18E-03 1.00E-03 1425900300051 84.0 4.20E-03 1.25E-03 1425900300052 85.0 8.06E-03 1.42E-03 1425900300053 86.0 1.50E-02 1.87E-03 1425900300054 87.0 1.43E-02 2.00E-03 1425900300055 88.0 2.23E-02 2.39E-03 1425900300056 89.0 2.79E-02 2.69E-03 1425900300057 90.0 3.52E-02 2.96E-03 1425900300058 91.0 4.08E-02 3.14E-03 1425900300059 92.0 5.06E-02 3.43E-03 1425900300060 93.0 5.48E-02 3.57E-03 1425900300061 94.0 5.95E-02 3.66E-03 1425900300062 95.0 6.39E-02 3.72E-03 1425900300063 96.0 5.97E-02 3.75E-03 1425900300064 97.0 6.32E-02 3.69E-03 1425900300065 98.0 6.14E-02 3.72E-03 1425900300066 99.0 5.99E-02 3.57E-03 1425900300067 100.0 5.91E-02 3.52E-03 1425900300068 101.0 5.51E-02 3.36E-03 1425900300069 102.0 5.20E-02 3.25E-03 1425900300070 103.0 4.75E-02 2.97E-03 1425900300071 104.0 3.90E-02 2.68E-03 1425900300072 105.0 3.01E-02 2.35E-03 1425900300073 106.0 2.17E-02 2.01E-03 1425900300074 107.0 1.65E-02 1.74E-03 1425900300075 108.0 1.08E-02 1.27E-03 1425900300076 109.0 6.03E-03 9.83E-04 1425900300077 110.0 4.20E-03 8.14E-04 1425900300078 111.0 1.76E-03 6.55E-04 1425900300079 112.0 1.63E-03 4.42E-04 1425900300080 113.0 8.13E-04 4.05E-04 1425900300081 114.0 4.06E-04 3.42E-04 1425900300082 115.0 6.77E-04 3.18E-04 1425900300083 116.0 2.71E-04 3.53E-04 1425900300084 117.0 5.42E-04 2.50E-04 1425900300085 118.0 2.03E-04 2.79E-04 1425900300086 119.0 2.03E-04 2.50E-04 1425900300087 120.0 5.42E-04 3.53E-04 1425900300088 121.0 2.71E-04 3.18E-04 1425900300089 122.0 6.77E-04 3.42E-04 1425900300090 123.0 4.06E-04 4.05E-04 1425900300091 124.0 8.13E-04 4.42E-04 1425900300092 125.0 1.63E-03 6.55E-04 1425900300093 126.0 1.76E-03 8.14E-04 1425900300094 127.0 4.20E-03 9.83E-04 1425900300095 128.0 6.03E-03 1.27E-03 1425900300096 129.0 1.08E-02 1.74E-03 1425900300097 130.0 1.65E-02 2.01E-03 1425900300098 131.0 2.17E-02 2.35E-03 1425900300099 132.0 3.01E-02 2.68E-03 1425900300100 133.0 3.90E-02 2.97E-03 1425900300101 134.0 4.75E-02 3.25E-03 1425900300102 135.0 5.20E-02 3.36E-03 1425900300103 136.0 5.51E-02 3.52E-03 1425900300104 137.0 5.91E-02 3.57E-03 1425900300105 138.0 5.99E-02 3.72E-03 1425900300106 139.0 6.14E-02 3.69E-03 1425900300107 140.0 6.32E-02 3.75E-03 1425900300108 141.0 5.97E-02 3.72E-03 1425900300109 142.0 6.39E-02 3.66E-03 1425900300110 143.0 5.95E-02 3.57E-03 1425900300111 144.0 5.48E-02 3.43E-03 1425900300112 145.0 5.06E-02 3.14E-03 1425900300113 146.0 4.08E-02 2.96E-03 1425900300114 147.0 3.52E-02 2.69E-03 1425900300115 148.0 2.79E-02 2.39E-03 1425900300116 149.0 2.23E-02 2.00E-03 1425900300117 150.0 1.43E-02 1.87E-03 1425900300118 151.0 1.50E-02 1.42E-03 1425900300119 152.0 8.06E-03 1.25E-03 1425900300120 153.0 4.20E-03 1.00E-03 1425900300121 154.0 3.18E-03 8.09E-04 1425900300122 155.0 2.57E-03 6.67E-04 1425900300123 156.0 1.76E-03 4.76E-04 1425900300124 157.0 7.45E-04 4.59E-04 1425900300125 158.0 6.10E-04 4.24E-04 1425900300126 159.0 5.42E-04 3.42E-04 1425900300127 160.0 2.03E-04 2.79E-04 1425900300128 161.0 2.03E-04 1.77E-04 1425900300129 162.0 4.74E-04 1.25E-04 1425900300130 163.0 6.77E-05 1425900300131 164.0 6.77E-05 1.53E-04 1425900300132 165.0 1.35E-04 8.83E-05 1425900300133 166.0 6.77E-05 1425900300134 169.0 1.35E-04 1425900300135 172.0 6.77E-05 1425900300136 ENDDATA 102 0 1425900300137 ENDSUBENT 136 0 1425900399999 SUBENT 14259004 20120816 13851425900400001 BIB 7 27 1425900400002 REACTION (92-U-235(N,F),PRE,FY/DE,FF,SPA/FCT) 1425900400003 Data times normalisation factor 2 1425900400004 EN-SEC (E,FF) 1425900400005 FACILITY (LINAC,1USARPI) Experiment performed at RPI 60-MeV 1425900400006 electron linac. 1425900400007 SAMPLE The 235U sample was made at Los Alamos National Labs 1425900400008 and was prepared by dissolving 99.98% 235U in 8M HNO3. 1425900400009 The solution was dried down and redissolved in absolute1425900400010 alcohol and 25.3+-0.5 mu-g was deposited in an area of 1425900400011 1 cm diameter on a polyimide film. The sample was 1425900400012 placed on cathode in the middle of the fission chamber 1425900400013 INC-SOURCE (PHOTO)Neutrons were produced through a (gamma,n) 1425900400014 reaction when electrons from the RPI 60-MeV electron 1425900400015 linac interact with a tantalum target, placed in the 1425900400016 center of lead slowing down spectrometer.The linac was 1425900400017 run at an average electron current of 8 mu-A, 1425900400018 delivering 58-MeV electrons in a pulse width of 200 ns 1425900400019 at 180 Hz.The neutron energy and flux are experimentaly1425900400020 known functions of slowing down time and electron beam 1425900400021 intensity. The neutron-energy resolution (FWHM)] in 1425900400022 the energy range of 0.1 eV to 1 keV was 1425900400023 approximately 35%. 1425900400024 STATUS (TABLE) Data presented in central part of fig.6 1425900400025 of the PR/C,81,014607 reference sent by author (C.R.) 1425900400026 HISTORY (20100617A) Added FCT to Reaction 1425900400027 (20120816A) SD: SF8=MXW -> SPA; SF7=FF added in 1425900400028 REACTION code 1425900400029 ENDBIB 27 0 1425900400030 COMMON 1 3 1425900400031 EN-MAX 1425900400032 EV 1425900400033 0.1 1425900400034 ENDCOMMON 3 0 1425900400035 DATA 2 169 1425900400036 E DATA 1425900400037 MEV PT/FIS/MEV 1425900400038 31.75 6.47E-05 1425900400039 32.25 3.23E-05 1425900400040 32.75 3.23E-05 1425900400041 33.25 3.23E-05 1425900400042 33.75 3.23E-05 1425900400043 34.25 3.23E-05 1425900400044 35.25 6.47E-05 1425900400045 35.75 3.23E-05 1425900400046 36.25 3.23E-05 1425900400047 36.75 3.23E-05 1425900400048 37.25 9.70E-05 1425900400049 37.75 9.70E-05 1425900400050 38.25 6.47E-05 1425900400051 38.75 6.47E-05 1425900400052 39.25 3.23E-05 1425900400053 40.25 1.62E-04 1425900400054 40.75 1.62E-04 1425900400055 41.25 1.29E-04 1425900400056 41.75 1.29E-04 1425900400057 42.25 9.70E-05 1425900400058 42.75 1.94E-04 1425900400059 43.25 1.29E-04 1425900400060 43.75 1.94E-04 1425900400061 44.25 1.94E-04 1425900400062 44.75 2.26E-04 1425900400063 45.25 1.62E-04 1425900400064 45.75 2.91E-04 1425900400065 46.25 1.62E-04 1425900400066 46.75 2.59E-04 1425900400067 47.25 2.91E-04 1425900400068 47.75 3.23E-04 1425900400069 48.25 2.59E-04 1425900400070 48.75 3.23E-04 1425900400071 49.25 2.91E-04 1425900400072 49.75 4.20E-04 1425900400073 50.25 3.23E-04 1425900400074 50.75 7.11E-04 1425900400075 51.25 5.50E-04 1425900400076 51.75 9.05E-04 1425900400077 52.25 1.16E-03 1425900400078 52.75 1.62E-03 1425900400079 53.25 2.30E-03 1425900400080 53.75 2.00E-03 1425900400081 54.25 3.01E-03 1425900400082 54.75 3.23E-03 1425900400083 55.25 3.14E-03 1425900400084 55.75 4.69E-03 1425900400085 56.25 4.72E-03 1425900400086 56.75 5.08E-03 1425900400087 57.25 6.08E-03 1425900400088 57.75 7.24E-03 1425900400089 58.25 8.80E-03 1425900400090 58.75 9.54E-03 1425900400091 59.25 1.01E-02 1425900400092 59.75 1.20E-02 1425900400093 60.25 1.39E-02 1425900400094 60.75 1.47E-02 1425900400095 61.25 1.67E-02 1425900400096 61.75 1.77E-02 1425900400097 62.25 1.71E-02 1425900400098 62.75 1.91E-02 1425900400099 63.25 2.00E-02 1425900400100 63.75 2.15E-02 1425900400101 64.25 2.21E-02 1425900400102 64.75 2.45E-02 1425900400103 65.25 2.41E-02 1425900400104 65.75 2.48E-02 1425900400105 66.25 2.52E-02 1425900400106 66.75 2.55E-02 1425900400107 67.25 2.70E-02 1425900400108 67.75 2.74E-02 1425900400109 68.25 2.74E-02 1425900400110 68.75 2.68E-02 1425900400111 69.25 2.66E-02 1425900400112 69.75 2.57E-02 1425900400113 70.25 2.54E-02 1425900400114 70.75 2.45E-02 1425900400115 71.25 2.20E-02 1425900400116 71.75 2.44E-02 1425900400117 72.25 2.38E-02 1425900400118 72.75 2.16E-02 1425900400119 73.25 2.22E-02 1425900400120 73.75 2.08E-02 1425900400121 74.25 2.06E-02 1425900400122 74.75 2.05E-02 1425900400123 75.25 1.96E-02 1425900400124 75.75 1.86E-02 1425900400125 76.25 1.60E-02 1425900400126 76.75 1.60E-02 1425900400127 77.25 1.51E-02 1425900400128 77.75 1.49E-02 1425900400129 78.25 1.37E-02 1425900400130 78.75 1.32E-02 1425900400131 79.25 1.28E-02 1425900400132 79.75 1.15E-02 1425900400133 80.25 1.10E-02 1425900400134 80.75 9.31E-03 1425900400135 81.25 9.93E-03 1425900400136 81.75 8.80E-03 1425900400137 82.25 8.05E-03 1425900400138 82.75 8.08E-03 1425900400139 83.25 6.27E-03 1425900400140 83.75 6.14E-03 1425900400141 84.25 5.43E-03 1425900400142 84.75 4.62E-03 1425900400143 85.25 3.82E-03 1425900400144 85.75 3.30E-03 1425900400145 86.25 3.72E-03 1425900400146 86.75 4.04E-03 1425900400147 87.25 3.27E-03 1425900400148 87.75 3.75E-03 1425900400149 88.25 3.72E-03 1425900400150 88.75 4.11E-03 1425900400151 89.25 4.14E-03 1425900400152 89.75 4.79E-03 1425900400153 90.25 5.21E-03 1425900400154 90.75 6.44E-03 1425900400155 91.25 7.79E-03 1425900400156 91.75 8.25E-03 1425900400157 92.25 9.09E-03 1425900400158 92.75 1.12E-02 1425900400159 93.25 1.14E-02 1425900400160 93.75 1.48E-02 1425900400161 94.25 1.67E-02 1425900400162 94.75 1.66E-02 1425900400163 95.25 1.97E-02 1425900400164 95.75 2.03E-02 1425900400165 96.25 2.13E-02 1425900400166 96.75 2.42E-02 1425900400167 97.25 2.68E-02 1425900400168 97.75 2.87E-02 1425900400169 98.25 3.25E-02 1425900400170 98.75 3.35E-02 1425900400171 99.25 3.23E-02 1425900400172 99.75 3.51E-02 1425900400173 100.25 3.55E-02 1425900400174 100.75 3.66E-02 1425900400175 101.25 3.68E-02 1425900400176 101.75 3.65E-02 1425900400177 102.25 3.87E-02 1425900400178 102.75 3.65E-02 1425900400179 103.25 3.85E-02 1425900400180 103.75 3.65E-02 1425900400181 104.25 3.34E-02 1425900400182 104.75 3.32E-02 1425900400183 105.25 3.22E-02 1425900400184 105.75 2.67E-02 1425900400185 106.25 2.41E-02 1425900400186 106.75 2.35E-02 1425900400187 107.25 2.14E-02 1425900400188 107.75 1.71E-02 1425900400189 108.25 1.59E-02 1425900400190 108.75 1.29E-02 1425900400191 109.25 1.20E-02 1425900400192 109.75 8.63E-03 1425900400193 110.25 6.86E-03 1425900400194 110.75 6.11E-03 1425900400195 111.25 4.59E-03 1425900400196 111.75 2.98E-03 1425900400197 112.25 2.88E-03 1425900400198 112.75 1.71E-03 1425900400199 113.25 1.00E-03 1425900400200 113.75 5.82E-04 1425900400201 114.25 5.17E-04 1425900400202 114.75 4.85E-04 1425900400203 115.25 2.26E-04 1425900400204 115.75 1.94E-04 1425900400205 116.25 9.70E-05 1425900400206 116.75 6.47E-05 1425900400207 ENDDATA 171 0 1425900400208 ENDSUBENT 207 0 1425900499999 SUBENT 14259005 20120816 13851425900500001 BIB 6 24 1425900500002 REACTION (92-U-235(N,F)MASS,SEC,FY,,SPA) 1425900500003 FACILITY (LINAC,1USARPI) Experiment performed at RPI 60-MeV 1425900500004 electron linac. 1425900500005 SAMPLE The 235U sample was made at Los Alamos National Labs 1425900500006 and was prepared by dissolving 99.98% 235U in 8M HNO3. 1425900500007 The solution was dried down and redissolved in absolute1425900500008 alcohol and 25.3+-0.5 mu-g was deposited in an area of 1425900500009 1 cm diameter on a polyimide film. The sample was 1425900500010 placed on cathode in the middle of the fission chamber 1425900500011 INC-SOURCE (PHOTO)Neutrons were produced through a (gamma,n) 1425900500012 reaction when electrons from the RPI 60-MeV electron 1425900500013 Linac interact with a tantalum target, placed in the 1425900500014 center of lead slowing down spectrometer.The Linac was 1425900500015 run at an average electron current of 8 mu-A, 1425900500016 delivering 58-MeV electrons in a pulse width of 200 ns 1425900500017 at 180 Hz.The neutron energy and flux are experimentaly1425900500018 known functions of slowing down time and electron beam 1425900500019 intensity. The neutron-energy resolution (FWHM)] in 1425900500020 the energy range of 0.1 eV to 1 keV was 1425900500021 approximately 35%. 1425900500022 STATUS (TABLE) Data presented in top part in fig.6 1425900500023 of the PR/C,81,014607 reference sent by author (C.R.) 1425900500024 Mass calculated from half-integers by compiler 1425900500025 HISTORY (20120816A) SD: SF8=MXW -> SPA 1425900500026 ENDBIB 24 0 1425900500027 COMMON 1 3 1425900500028 EN-MAX 1425900500029 EV 1425900500030 0.1 1425900500031 ENDCOMMON 3 0 1425900500032 DATA 2 91 1425900500033 MASS DATA 1425900500034 NO-DIM PRD/FIS 1425900500035 73.0 3.92E-04 1425900500036 74.0 1.78E-04 1425900500037 75.0 4.63E-04 1425900500038 76.0 9.26E-04 1425900500039 77.0 6.05E-04 1425900500040 78.0 1.18E-03 1425900500041 79.0 3.31E-03 1425900500042 80.0 3.42E-03 1425900500043 81.0 5.49E-03 1425900500044 82.0 7.44E-03 1425900500045 83.0 1.28E-02 1425900500046 84.0 1.84E-02 1425900500047 85.0 2.36E-02 1425900500048 86.0 3.18E-02 1425900500049 87.0 3.72E-02 1425900500050 88.0 5.62E-02 1425900500051 89.0 5.10E-02 1425900500052 90.0 6.47E-02 1425900500053 91.0 5.80E-02 1425900500054 92.0 6.74E-02 1425900500055 93.0 6.24E-02 1425900500056 94.0 6.91E-02 1425900500057 95.0 5.70E-02 1425900500058 96.0 6.18E-02 1425900500059 97.0 5.41E-02 1425900500060 98.0 5.32E-02 1425900500061 99.0 4.67E-02 1425900500062 100.0 4.47E-02 1425900500063 101.0 3.43E-02 1425900500064 102.0 2.49E-02 1425900500065 103.0 1.72E-02 1425900500066 104.0 1.20E-02 1425900500067 105.0 7.48E-03 1425900500068 106.0 3.60E-03 1425900500069 107.0 2.56E-03 1425900500070 108.0 1.10E-03 1425900500071 109.0 6.77E-04 1425900500072 110.0 6.77E-04 1425900500073 111.0 4.27E-04 1425900500074 112.0 3.92E-04 1425900500075 113.0 3.92E-04 1425900500076 114.0 2.14E-04 1425900500077 115.0 3.56E-04 1425900500078 116.0 4.63E-04 1425900500079 117.0 2.14E-04 1425900500080 118.0 5.70E-04 1425900500081 119.0 7.84E-04 1425900500082 120.0 6.41E-04 1425900500083 121.0 3.21E-04 1425900500084 122.0 8.55E-04 1425900500085 123.0 1.89E-03 1425900500086 124.0 2.71E-03 1425900500087 125.0 5.70E-03 1425900500088 126.0 7.80E-03 1425900500089 127.0 1.39E-02 1425900500090 128.0 1.83E-02 1425900500091 129.0 2.72E-02 1425900500092 130.0 3.40E-02 1425900500093 131.0 5.11E-02 1425900500094 132.0 5.14E-02 1425900500095 133.0 5.81E-02 1425900500096 134.0 6.41E-02 1425900500097 135.0 6.16E-02 1425900500098 136.0 6.66E-02 1425900500099 137.0 6.39E-02 1425900500100 138.0 7.33E-02 1425900500101 139.0 5.90E-02 1425900500102 140.0 6.04E-02 1425900500103 141.0 5.20E-02 1425900500104 142.0 5.23E-02 1425900500105 143.0 4.08E-02 1425900500106 144.0 3.78E-02 1425900500107 145.0 2.67E-02 1425900500108 146.0 2.19E-02 1425900500109 147.0 1.49E-02 1425900500110 148.0 9.19E-03 1425900500111 149.0 6.80E-03 1425900500112 150.0 3.81E-03 1425900500113 151.0 2.64E-03 1425900500114 152.0 2.64E-03 1425900500115 153.0 1.25E-03 1425900500116 154.0 1.14E-03 1425900500117 155.0 4.99E-04 1425900500118 156.0 1.78E-04 1425900500119 157.0 2.49E-04 1425900500120 158.0 2.14E-04 1425900500121 159.0 1.07E-04 1425900500122 160.0 1.07E-04 1425900500123 161.0 3.56E-05 1425900500124 162.0 7.12E-05 1425900500125 163.0 3.56E-05 1425900500126 ENDDATA 93 0 1425900500127 ENDSUBENT 126 0 1425900599999 SUBENT 14259006 20120816 13851425900600001 BIB 6 26 1425900600002 REACTION (92-U-235(N,F)MASS,SEC,FY,,AV) 1425900600003 The incident-neutron-energy range for the data in this1425900600004 resonance group is primarily 225-275 eV. 1425900600005 FACILITY (LINAC,1USARPI) Experiment performed at RPI 60-MeV 1425900600006 electron linac. 1425900600007 SAMPLE The 235U sample was made at Los Alamos National Labs 1425900600008 and was prepared by dissolving 99.98% 235U in 8M HNO3. 1425900600009 The solution was dried down and redissolved in absolute1425900600010 alcohol and 25.3+-0.5 mu-g was deposited in an area of 1425900600011 1 cm diameter on a polyimide film. The sample was 1425900600012 placed on cathode in the middle of the fission chamber 1425900600013 INC-SOURCE (PHOTO)Neutrons were produced through a (gamma,n) 1425900600014 reaction when electrons from the RPI 60-MeV electron 1425900600015 Linac interact with a tantalum target, placed in the 1425900600016 center of lead slowing down spectrometer.The Linac was 1425900600017 run at an average electron current of 8 mu-A, 1425900600018 delivering 58-MeV electrons in a pulse width of 200 ns 1425900600019 at 180 Hz.The neutron energy and flux are experimentaly1425900600020 known functions of slowing down time and electron beam 1425900600021 intensity. The neutron-energy resolution (FWHM)] in 1425900600022 the energy range of 0.1 eV to 1 keV was 1425900600023 approximately 35%. 1425900600024 STATUS (TABLE) Data presented in fig.14 of the PR/C,81,0146071425900600025 reference sent by author (C.R.) 1425900600026 Mass calculated from half-integers by compiler 1425900600027 ERR-ANALYS (ERR-S) Statistical uncertainty 1425900600028 ENDBIB 26 0 1425900600029 COMMON 2 3 1425900600030 EN-MIN EN-MAX 1425900600031 EV EV 1425900600032 225.0 275.0 1425900600033 ENDCOMMON 3 0 1425900600034 DATA 3 86 1425900600035 MASS DATA ERR-S 1425900600036 NO-DIM PRD/FIS PRD/FIS 1425900600037 75.0 1.39E-04 1.39E-04 1425900600038 76.0 2.78E-04 1.96E-04 1425900600039 77.0 8.33E-04 3.40E-04 1425900600040 79.0 9.72E-04 3.67E-04 1425900600041 80.0 1.67E-03 4.81E-04 1425900600042 81.0 1.67E-03 4.81E-04 1425900600043 82.0 2.78E-03 6.21E-04 1425900600044 83.0 4.30E-03 7.73E-04 1425900600045 84.0 7.22E-03 1.00E-03 1425900600046 85.0 1.01E-02 1.19E-03 1425900600047 86.0 1.60E-02 1.49E-03 1425900600048 87.0 1.81E-02 1.58E-03 1425900600049 88.0 2.71E-02 1.94E-03 1425900600050 89.0 3.28E-02 2.13E-03 1425900600051 90.0 3.78E-02 2.29E-03 1425900600052 91.0 4.49E-02 2.50E-03 1425900600053 92.0 5.40E-02 2.74E-03 1425900600054 93.0 5.78E-02 2.83E-03 1425900600055 94.0 5.94E-02 2.87E-03 1425900600056 95.0 6.30E-02 2.96E-03 1425900600057 96.0 7.07E-02 3.13E-03 1425900600058 97.0 6.08E-02 2.91E-03 1425900600059 98.0 6.17E-02 2.93E-03 1425900600060 99.0 5.64E-02 2.80E-03 1425900600061 100.0 5.85E-02 2.85E-03 1425900600062 101.0 5.14E-02 2.67E-03 1425900600063 102.0 4.67E-02 2.55E-03 1425900600064 103.0 4.04E-02 2.37E-03 1425900600065 104.0 3.18E-02 2.10E-03 1425900600066 105.0 2.50E-02 1.86E-03 1425900600067 106.0 2.00E-02 1.67E-03 1425900600068 107.0 1.53E-02 1.46E-03 1425900600069 108.0 7.64E-03 1.03E-03 1425900600070 109.0 5.14E-03 8.45E-04 1425900600071 110.0 2.92E-03 6.36E-04 1425900600072 111.0 1.39E-03 4.39E-04 1425900600073 112.0 1.67E-03 4.81E-04 1425900600074 113.0 5.55E-04 2.78E-04 1425900600075 114.0 5.55E-04 2.78E-04 1425900600076 115.0 0.00E+00 0.00E+00 1425900600077 116.0 1.39E-04 1.39E-04 1425900600078 117.0 4.17E-04 2.40E-04 1425900600079 118.0 5.55E-04 2.78E-04 1425900600080 119.0 4.17E-04 2.40E-04 1425900600081 120.0 1.39E-04 1.39E-04 1425900600082 121.0 0.00E+00 0.00E+00 1425900600083 122.0 5.55E-04 2.78E-04 1425900600084 123.0 5.55E-04 2.78E-04 1425900600085 124.0 1.67E-03 4.81E-04 1425900600086 125.0 1.39E-03 4.39E-04 1425900600087 126.0 2.92E-03 6.36E-04 1425900600088 127.0 5.14E-03 8.45E-04 1425900600089 128.0 7.64E-03 1.03E-03 1425900600090 129.0 1.53E-02 1.46E-03 1425900600091 130.0 2.00E-02 1.67E-03 1425900600092 131.0 2.50E-02 1.86E-03 1425900600093 132.0 3.18E-02 2.10E-03 1425900600094 133.0 4.04E-02 2.37E-03 1425900600095 134.0 4.67E-02 2.55E-03 1425900600096 135.0 5.14E-02 2.67E-03 1425900600097 136.0 5.85E-02 2.85E-03 1425900600098 137.0 5.64E-02 2.80E-03 1425900600099 138.0 6.17E-02 2.93E-03 1425900600100 139.0 6.08E-02 2.91E-03 1425900600101 140.0 7.07E-02 3.13E-03 1425900600102 141.0 6.30E-02 2.96E-03 1425900600103 142.0 5.94E-02 2.87E-03 1425900600104 143.0 5.78E-02 2.83E-03 1425900600105 144.0 5.40E-02 2.74E-03 1425900600106 145.0 4.49E-02 2.50E-03 1425900600107 146.0 3.78E-02 2.29E-03 1425900600108 147.0 3.28E-02 2.13E-03 1425900600109 148.0 2.71E-02 1.94E-03 1425900600110 149.0 1.81E-02 1.58E-03 1425900600111 150.0 1.60E-02 1.49E-03 1425900600112 151.0 1.01E-02 1.19E-03 1425900600113 152.0 7.22E-03 1.00E-03 1425900600114 153.0 4.30E-03 7.73E-04 1425900600115 154.0 2.78E-03 6.21E-04 1425900600116 155.0 1.67E-03 4.81E-04 1425900600117 156.0 1.67E-03 4.81E-04 1425900600118 157.0 9.72E-04 3.67E-04 1425900600119 158.0 0.00E+00 0.00E+00 1425900600120 159.0 8.33E-04 3.40E-04 1425900600121 160.0 2.78E-04 1.96E-04 1425900600122 161.0 1.39E-04 1.39E-04 1425900600123 ENDDATA 88 0 1425900600124 ENDSUBENT 123 0 1425900699999 SUBENT 14259007 20120816 13851425900700001 BIB 6 26 1425900700002 REACTION (92-U-235(N,F)MASS,SEC,FY,,AV) 1425900700003 Resonance region includes the incident-neutron-energy 1425900700004 range around 511-675 eV. 1425900700005 FACILITY (LINAC,1USARPI) Experiment performed at RPI 60-MeV 1425900700006 electron linac. 1425900700007 SAMPLE The 235U sample was made at Los Alamos National Labs 1425900700008 and was prepared by dissolving 99.98% 235U in 8M HNO3. 1425900700009 The solution was dried down and redissolved in absolute1425900700010 alcohol and 25.3+-0.5 mu-g was deposited in an area of 1425900700011 1 cm diameter on a polyimide film. The sample was 1425900700012 placed on cathode in the middle of the fission chamber 1425900700013 INC-SOURCE (PHOTO)Neutrons were produced through a (gamma,n) 1425900700014 reaction when electrons from the RPI 60-MeV electron 1425900700015 linac interact with a tantalum target, placed in the 1425900700016 center of lead slowing down spectrometer.The linac was 1425900700017 run at an average electron current of 8 mu-A, 1425900700018 delivering 58-MeV electrons in a pulse width of 200 ns 1425900700019 at 180 Hz.The neutron energy and flux are experimentaly1425900700020 known functions of slowing down time and electron beam 1425900700021 intensity. The neutron-energy resolution (FWHM)] in 1425900700022 the energy range of 0.1 eV to 1 keV was 1425900700023 approximately 35%. 1425900700024 STATUS (TABLE) Data presented in fig.15 of the PR/C,81,0146071425900700025 reference sent by author (C.R.) 1425900700026 Mass calculated from half-integers by compiler 1425900700027 ERR-ANALYS (ERR-S) Statistical uncertainty 1425900700028 ENDBIB 26 0 1425900700029 COMMON 2 3 1425900700030 EN-MIN EN-MAX 1425900700031 EV EV 1425900700032 511.0 675.0 1425900700033 ENDCOMMON 3 0 1425900700034 DATA 3 93 1425900700035 MASS DATA ERR-S 1425900700036 NO-DIM PRD/FIS PRD/FIS 1425900700037 71.0 3.64E-05 6.03E-03 1425900700038 72.0 1.09E-04 3.48E-03 1425900700039 74.0 1.09E-04 3.48E-03 1425900700040 75.0 2.55E-04 2.28E-03 1425900700041 76.0 1.82E-04 2.70E-03 1425900700042 77.0 3.64E-04 1.91E-03 1425900700043 78.0 7.64E-04 1.32E-03 1425900700044 79.0 9.10E-04 1.21E-03 1425900700045 80.0 1.16E-03 1.07E-03 1425900700046 81.0 2.07E-03 7.99E-04 1425900700047 82.0 2.73E-03 6.97E-04 1425900700048 83.0 4.26E-03 5.58E-04 1425900700049 84.0 6.73E-03 4.44E-04 1425900700050 85.0 9.79E-03 3.68E-04 1425900700051 86.0 1.47E-02 3.00E-04 1425900700052 87.0 1.94E-02 2.61E-04 1425900700053 88.0 2.39E-02 2.35E-04 1425900700054 89.0 3.44E-02 1.96E-04 1425900700055 90.0 3.72E-02 1.89E-04 1425900700056 91.0 5.15E-02 1.60E-04 1425900700057 92.0 4.88E-02 1.65E-04 1425900700058 93.0 5.93E-02 1.49E-04 1425900700059 94.0 5.84E-02 1.51E-04 1425900700060 95.0 6.57E-02 1.42E-04 1425900700061 96.0 6.22E-02 1.46E-04 1425900700062 97.0 6.48E-02 1.43E-04 1425900700063 98.0 6.00E-02 1.49E-04 1425900700064 99.0 6.12E-02 1.47E-04 1425900700065 100.0 5.48E-02 1.56E-04 1425900700066 101.0 5.46E-02 1.56E-04 1425900700067 102.0 4.46E-02 1.72E-04 1425900700068 103.0 4.48E-02 1.72E-04 1425900700069 104.0 3.22E-02 2.03E-04 1425900700070 105.0 2.55E-02 2.28E-04 1425900700071 106.0 1.85E-02 2.68E-04 1425900700072 107.0 1.34E-02 3.14E-04 1425900700073 108.0 7.39E-03 4.23E-04 1425900700074 109.0 4.95E-03 5.17E-04 1425900700075 110.0 3.06E-03 6.58E-04 1425900700076 111.0 1.53E-03 9.31E-04 1425900700077 112.0 9.10E-04 1.21E-03 1425900700078 113.0 6.19E-04 1.46E-03 1425900700079 114.0 5.82E-04 1.51E-03 1425900700080 115.0 6.55E-04 1.42E-03 1425900700081 116.0 4.00E-04 1.82E-03 1425900700082 117.0 2.55E-04 2.28E-03 1425900700083 118.0 4.37E-04 1.74E-03 1425900700084 119.0 2.55E-04 2.28E-03 1425900700085 120.0 4.00E-04 1.82E-03 1425900700086 121.0 6.55E-04 1.42E-03 1425900700087 122.0 5.82E-04 1.51E-03 1425900700088 123.0 6.19E-04 1.46E-03 1425900700089 124.0 9.10E-04 1.21E-03 1425900700090 125.0 1.53E-03 9.31E-04 1425900700091 126.0 3.06E-03 6.58E-04 1425900700092 127.0 4.95E-03 5.17E-04 1425900700093 128.0 7.39E-03 4.23E-04 1425900700094 129.0 1.34E-02 3.14E-04 1425900700095 130.0 1.85E-02 2.68E-04 1425900700096 131.0 2.55E-02 2.28E-04 1425900700097 132.0 3.22E-02 2.03E-04 1425900700098 133.0 4.48E-02 1.72E-04 1425900700099 134.0 4.46E-02 1.72E-04 1425900700100 135.0 5.46E-02 1.56E-04 1425900700101 136.0 5.48E-02 1.56E-04 1425900700102 137.0 6.12E-02 1.47E-04 1425900700103 138.0 6.00E-02 1.49E-04 1425900700104 139.0 6.48E-02 1.43E-04 1425900700105 140.0 6.22E-02 1.46E-04 1425900700106 141.0 6.57E-02 1.42E-04 1425900700107 142.0 5.84E-02 1.51E-04 1425900700108 143.0 5.93E-02 1.49E-04 1425900700109 144.0 4.88E-02 1.65E-04 1425900700110 145.0 5.15E-02 1.60E-04 1425900700111 146.0 3.72E-02 1.89E-04 1425900700112 147.0 3.44E-02 1.96E-04 1425900700113 148.0 2.39E-02 2.35E-04 1425900700114 149.0 1.94E-02 2.61E-04 1425900700115 150.0 1.47E-02 3.00E-04 1425900700116 151.0 9.79E-03 3.68E-04 1425900700117 152.0 6.73E-03 4.44E-04 1425900700118 153.0 4.26E-03 5.58E-04 1425900700119 154.0 2.73E-03 6.97E-04 1425900700120 155.0 2.07E-03 7.99E-04 1425900700121 156.0 1.16E-03 1.07E-03 1425900700122 157.0 9.10E-04 1.21E-03 1425900700123 158.0 7.64E-04 1.32E-03 1425900700124 159.0 3.64E-04 1.91E-03 1425900700125 160.0 1.82E-04 2.70E-03 1425900700126 161.0 2.55E-04 2.28E-03 1425900700127 162.0 1.09E-04 3.48E-03 1425900700128 164.0 1.09E-04 3.48E-03 1425900700129 165.0 3.64E-05 6.03E-03 1425900700130 ENDDATA 95 0 1425900700131 ENDSUBENT 130 0 1425900799999 SUBENT 14259008 20100128 13611425900800001 BIB 3 5 1425900800002 REACTION (98-CF-252(0,F)MASS,PRE,FY) 1425900800003 STATUS (TABLE) Data presented bottom in fig.3 of 1425900800004 the PR/C reference sent by author (C.R.) 1425900800005 Mass calculated from half-integers by compiler 1425900800006 ERR-ANALYS (ERR-S) Statistical uncertainty 1425900800007 ENDBIB 5 0 1425900800008 NOCOMMON 0 0 1425900800009 DATA 3 88 1425900800010 MASS DATA ERR-S 1425900800011 NO-DIM PRD/FIS PRD/FIS 1425900800012 80.0 1.67E-05 1.70E-05 1425900800013 81.0 1.67E-05 1.70E-05 1425900800014 84.0 6.70E-05 3.39E-05 1425900800015 85.0 2.18E-04 6.11E-05 1425900800016 86.0 2.34E-04 6.34E-05 1425900800017 87.0 5.86E-04 1.00E-04 1425900800018 88.0 7.37E-04 1.12E-04 1425900800019 89.0 9.88E-04 1.30E-04 1425900800020 90.0 1.76E-03 1.74E-04 1425900800021 91.0 2.21E-03 1.95E-04 1425900800022 92.0 3.15E-03 2.32E-04 1425900800023 93.0 4.67E-03 2.83E-04 1425900800024 94.0 6.16E-03 3.25E-04 1425900800025 95.0 7.79E-03 3.66E-04 1425900800026 96.0 1.16E-02 4.47E-04 1425900800027 97.0 1.32E-02 4.76E-04 1425900800028 98.0 1.68E-02 5.37E-04 1425900800029 99.0 2.03E-02 5.90E-04 1425900800030 100.0 2.57E-02 6.64E-04 1425900800031 101.0 3.06E-02 7.25E-04 1425900800032 102.0 3.69E-02 7.96E-04 1425900800033 103.0 4.39E-02 8.68E-04 1425900800034 104.0 4.98E-02 9.24E-04 1425900800035 105.0 5.45E-02 9.67E-04 1425900800036 106.0 5.82E-02 9.99E-04 1425900800037 107.0 6.00E-02 1.02E-03 1425900800038 108.0 6.11E-02 1.02E-03 1425900800039 109.0 5.98E-02 1.01E-03 1425900800040 110.0 5.53E-02 9.74E-04 1425900800041 111.0 5.33E-02 9.56E-04 1425900800042 112.0 4.82E-02 9.10E-04 1425900800043 113.0 4.37E-02 8.66E-04 1425900800044 114.0 3.90E-02 8.18E-04 1425900800045 115.0 3.44E-02 7.69E-04 1425900800046 116.0 3.00E-02 7.17E-04 1425900800047 117.0 2.59E-02 6.66E-04 1425900800048 118.0 2.07E-02 5.96E-04 1425900800049 119.0 1.70E-02 5.40E-04 1425900800050 120.0 1.26E-02 4.65E-04 1425900800051 121.0 8.72E-03 3.87E-04 1425900800052 122.0 5.39E-03 3.04E-04 1425900800053 123.0 3.90E-03 2.59E-04 1425900800054 124.0 3.38E-03 2.41E-04 1425900800055 125.0 3.28E-03 2.37E-04 1425900800056 126.0 3.28E-03 2.37E-04 1425900800057 127.0 3.38E-03 2.41E-04 1425900800058 128.0 3.90E-03 2.59E-04 1425900800059 129.0 5.39E-03 3.04E-04 1425900800060 130.0 8.72E-03 3.87E-04 1425900800061 131.0 1.26E-02 4.65E-04 1425900800062 132.0 1.70E-02 5.40E-04 1425900800063 133.0 2.07E-02 5.96E-04 1425900800064 134.0 2.59E-02 6.66E-04 1425900800065 135.0 3.00E-02 7.17E-04 1425900800066 136.0 3.44E-02 7.69E-04 1425900800067 137.0 3.90E-02 8.18E-04 1425900800068 138.0 4.37E-02 8.66E-04 1425900800069 139.0 4.82E-02 9.10E-04 1425900800070 140.0 5.33E-02 9.56E-04 1425900800071 141.0 5.53E-02 9.74E-04 1425900800072 142.0 5.98E-02 1.01E-03 1425900800073 143.0 6.11E-02 1.02E-03 1425900800074 144.0 6.00E-02 1.02E-03 1425900800075 145.0 5.82E-02 9.99E-04 1425900800076 146.0 5.45E-02 9.67E-04 1425900800077 147.0 4.98E-02 9.24E-04 1425900800078 148.0 4.39E-02 8.68E-04 1425900800079 149.0 3.69E-02 7.96E-04 1425900800080 150.0 3.06E-02 7.25E-04 1425900800081 151.0 2.57E-02 6.64E-04 1425900800082 152.0 2.03E-02 5.90E-04 1425900800083 153.0 1.68E-02 5.37E-04 1425900800084 154.0 1.32E-02 4.76E-04 1425900800085 155.0 1.16E-02 4.47E-04 1425900800086 156.0 7.79E-03 3.66E-04 1425900800087 157.0 6.16E-03 3.25E-04 1425900800088 158.0 4.67E-03 2.83E-04 1425900800089 159.0 3.15E-03 2.32E-04 1425900800090 160.0 2.21E-03 1.95E-04 1425900800091 161.0 1.76E-03 1.74E-04 1425900800092 162.0 9.88E-04 1.30E-04 1425900800093 163.0 7.37E-04 1.12E-04 1425900800094 164.0 5.86E-04 1.00E-04 1425900800095 165.0 2.34E-04 6.34E-05 1425900800096 166.0 2.18E-04 6.11E-05 1425900800097 167.0 6.70E-05 3.39E-05 1425900800098 170.0 1.67E-05 1.70E-05 1425900800099 171.0 1.67E-05 1.70E-05 1425900800100 ENDDATA 90 0 1425900800101 ENDSUBENT 100 0 1425900899999 SUBENT 14259009 20100128 13611425900900001 BIB 2 4 1425900900002 REACTION (98-CF-252(0,F)MASS,SEC,FY) 1425900900003 STATUS (TABLE) Data presented in fig.3 of the PR/C reference 1425900900004 sent by author (C.R.) 1425900900005 Mass calculated from half-integers by compiler 1425900900006 ENDBIB 4 0 1425900900007 NOCOMMON 0 0 1425900900008 DATA 2 80 1425900900009 MASS DATA 1425900900010 NO-DIM PRD/FIS 1425900900011 83.0 2.33E-04 1425900900012 84.0 2.33E-04 1425900900013 85.0 3.55E-04 1425900900014 86.0 4.55E-04 1425900900015 87.0 8.10E-04 1425900900016 88.0 1.24E-03 1425900900017 89.0 1.81E-03 1425900900018 90.0 2.21E-03 1425900900019 91.0 3.18E-03 1425900900020 92.0 4.48E-03 1425900900021 93.0 5.94E-03 1425900900022 94.0 8.17E-03 1425900900023 95.0 1.01E-02 1425900900024 96.0 1.45E-02 1425900900025 97.0 1.70E-02 1425900900026 98.0 2.13E-02 1425900900027 99.0 2.75E-02 1425900900028 100.0 3.23E-02 1425900900029 101.0 3.89E-02 1425900900030 102.0 4.70E-02 1425900900031 103.0 5.39E-02 1425900900032 104.0 6.05E-02 1425900900033 105.0 6.47E-02 1425900900034 106.0 6.62E-02 1425900900035 107.0 6.70E-02 1425900900036 108.0 6.52E-02 1425900900037 109.0 5.98E-02 1425900900038 110.0 5.71E-02 1425900900039 111.0 4.99E-02 1425900900040 112.0 4.50E-02 1425900900041 113.0 3.88E-02 1425900900042 114.0 3.36E-02 1425900900043 115.0 2.71E-02 1425900900044 116.0 2.29E-02 1425900900045 117.0 1.72E-02 1425900900046 118.0 1.29E-02 1425900900047 119.0 5.65E-03 1425900900048 120.0 4.20E-03 1425900900049 121.0 3.81E-03 1425900900050 122.0 1.96E-03 1425900900051 123.0 2.19E-03 1425900900052 124.0 2.32E-03 1425900900053 125.0 2.16E-03 1425900900054 126.0 2.19E-03 1425900900055 127.0 2.94E-03 1425900900056 128.0 3.02E-03 1425900900057 129.0 3.03E-03 1425900900058 130.0 4.35E-03 1425900900059 131.0 1.36E-02 1425900900060 132.0 1.70E-02 1425900900061 133.0 2.27E-02 1425900900062 134.0 2.68E-02 1425900900063 135.0 3.30E-02 1425900900064 136.0 3.84E-02 1425900900065 137.0 4.43E-02 1425900900066 138.0 4.94E-02 1425900900067 139.0 5.64E-02 1425900900068 140.0 5.91E-02 1425900900069 141.0 6.39E-02 1425900900070 142.0 6.68E-02 1425900900071 143.0 6.54E-02 1425900900072 144.0 6.46E-02 1425900900073 145.0 6.05E-02 1425900900074 146.0 5.44E-02 1425900900075 147.0 4.74E-02 1425900900076 148.0 3.93E-02 1425900900077 149.0 3.30E-02 1425900900078 150.0 2.80E-02 1425900900079 151.0 2.23E-02 1425900900080 152.0 1.73E-02 1425900900081 153.0 1.48E-02 1425900900082 154.0 1.09E-02 1425900900083 155.0 8.18E-03 1425900900084 156.0 6.68E-03 1425900900085 157.0 4.46E-03 1425900900086 158.0 3.58E-03 1425900900087 159.0 2.39E-03 1425900900088 160.0 1.86E-03 1425900900089 161.0 1.36E-03 1425900900090 162.0 8.65E-04 1425900900091 ENDDATA 82 0 1425900900092 ENDSUBENT 91 0 1425900999999 SUBENT 14259010 20120816 13851425901000001 BIB 4 5 1425901000002 REACTION (98-CF-252(0,F),PRE,FY/DE,FF) 1425901000003 EN-SEC (E,FF) 1425901000004 STATUS (TABLE) Data presented in fig.3 of the PR/C reference 1425901000005 sent by author (C.R.) 1425901000006 HISTORY (20120816A) SD: SF7=FF added in REACTION code 1425901000007 ENDBIB 5 0 1425901000008 NOCOMMON 0 0 1425901000009 DATA 2 140 1425901000010 E DATA 1425901000011 MEV PT/FIS/MEV 1425901000012 50.0 3.43E-05 1425901000013 50.5 1.72E-05 1425901000014 51.0 1.72E-05 1425901000015 51.5 3.43E-05 1425901000016 52.5 3.43E-05 1425901000017 53.0 1.72E-05 1425901000018 53.5 3.43E-05 1425901000019 54.0 8.58E-05 1425901000020 54.5 1.37E-04 1425901000021 55.0 6.87E-05 1425901000022 55.5 1.89E-04 1425901000023 56.0 1.72E-04 1425901000024 56.5 3.43E-04 1425901000025 57.0 3.95E-04 1425901000026 57.5 3.78E-04 1425901000027 58.0 5.66E-04 1425901000028 58.5 7.21E-04 1425901000029 59.0 7.21E-04 1425901000030 59.5 1.12E-03 1425901000031 60.0 1.29E-03 1425901000032 60.5 1.42E-03 1425901000033 61.0 1.65E-03 1425901000034 61.5 2.16E-03 1425901000035 62.0 2.35E-03 1425901000036 62.5 2.80E-03 1425901000037 63.0 2.87E-03 1425901000038 63.5 3.79E-03 1425901000039 64.0 3.78E-03 1425901000040 64.5 4.69E-03 1425901000041 65.0 5.10E-03 1425901000042 65.5 5.66E-03 1425901000043 66.0 6.78E-03 1425901000044 66.5 6.78E-03 1425901000045 67.0 8.53E-03 1425901000046 67.5 8.84E-03 1425901000047 68.0 9.53E-03 1425901000048 68.5 1.03E-02 1425901000049 69.0 1.12E-02 1425901000050 69.5 1.22E-02 1425901000051 70.0 1.36E-02 1425901000052 70.5 1.53E-02 1425901000053 71.0 1.57E-02 1425901000054 71.5 1.67E-02 1425901000055 72.0 1.73E-02 1425901000056 72.5 1.94E-02 1425901000057 73.0 1.96E-02 1425901000058 73.5 2.03E-02 1425901000059 74.0 2.19E-02 1425901000060 74.5 2.37E-02 1425901000061 75.0 2.31E-02 1425901000062 75.5 2.49E-02 1425901000063 76.0 2.60E-02 1425901000064 76.5 2.70E-02 1425901000065 77.0 2.74E-02 1425901000066 77.5 2.64E-02 1425901000067 78.0 2.77E-02 1425901000068 78.5 2.68E-02 1425901000069 79.0 2.70E-02 1425901000070 79.5 2.68E-02 1425901000071 80.0 2.59E-02 1425901000072 80.5 2.58E-02 1425901000073 81.0 2.60E-02 1425901000074 81.5 2.37E-02 1425901000075 82.0 2.41E-02 1425901000076 82.5 2.17E-02 1425901000077 83.0 2.24E-02 1425901000078 83.5 2.12E-02 1425901000079 84.0 2.04E-02 1425901000080 84.5 1.89E-02 1425901000081 85.0 1.93E-02 1425901000082 85.5 1.78E-02 1425901000083 86.0 1.69E-02 1425901000084 86.5 1.52E-02 1425901000085 87.0 1.58E-02 1425901000086 87.5 1.39E-02 1425901000087 88.0 1.32E-02 1425901000088 88.5 1.37E-02 1425901000089 89.0 1.23E-02 1425901000090 89.5 1.27E-02 1425901000091 90.0 1.17E-02 1425901000092 90.5 1.16E-02 1425901000093 91.0 1.12E-02 1425901000094 91.5 1.25E-02 1425901000095 92.0 1.15E-02 1425901000096 92.5 1.21E-02 1425901000097 93.0 1.31E-02 1425901000098 93.5 1.26E-02 1425901000099 94.0 1.45E-02 1425901000100 94.5 1.41E-02 1425901000101 95.0 1.50E-02 1425901000102 95.5 1.61E-02 1425901000103 96.0 1.73E-02 1425901000104 96.5 1.68E-02 1425901000105 97.0 1.90E-02 1425901000106 97.5 2.02E-02 1425901000107 98.0 2.06E-02 1425901000108 98.5 2.25E-02 1425901000109 99.0 2.32E-02 1425901000110 99.5 2.48E-02 1425901000111 100.0 2.52E-02 1425901000112 100.5 2.65E-02 1425901000113 101.0 2.88E-02 1425901000114 101.5 2.92E-02 1425901000115 102.0 2.99E-02 1425901000116 102.5 2.99E-02 1425901000117 103.0 3.00E-02 1425901000118 103.5 3.12E-02 1425901000119 104.0 3.18E-02 1425901000120 104.5 3.24E-02 1425901000121 105.0 3.18E-02 1425901000122 105.5 3.25E-02 1425901000123 106.0 3.06E-02 1425901000124 106.5 2.99E-02 1425901000125 107.0 2.80E-02 1425901000126 107.5 2.75E-02 1425901000127 108.0 2.63E-02 1425901000128 108.5 2.49E-02 1425901000129 109.0 2.23E-02 1425901000130 109.5 2.20E-02 1425901000131 110.0 1.98E-02 1425901000132 110.5 1.89E-02 1425901000133 111.0 1.78E-02 1425901000134 111.5 1.55E-02 1425901000135 112.0 1.36E-02 1425901000136 112.5 1.23E-02 1425901000137 113.0 1.10E-02 1425901000138 113.5 9.87E-03 1425901000139 114.0 8.44E-03 1425901000140 114.5 7.04E-03 1425901000141 115.0 6.37E-03 1425901000142 115.5 5.25E-03 1425901000143 116.0 4.07E-03 1425901000144 116.5 3.12E-03 1425901000145 117.0 2.81E-03 1425901000146 117.5 2.32E-03 1425901000147 118.0 1.73E-03 1425901000148 118.5 1.63E-03 1425901000149 119.0 8.41E-04 1425901000150 119.5 9.27E-04 1425901000151 120.0 5.32E-04 1425901000152 ENDDATA 142 0 1425901000153 ENDSUBENT 152 0 1425901099999 ENDENTRY 10 0 1425999999999