ENTRY 10757 20091112 13601075700000001 SUBENT 10757001 20091112 13601075700100001 BIB 7 11 1075700100002 INSTITUTE (1USAANL) 1075700100003 REFERENCE (R,ANL-NDM-37,197712) 1075700100004 AUTHOR (D.L.Smith,J.W.Meadows) 1075700100005 TITLE Neutron inelastic scattering studies for lead 204 1075700100006 FACILITY (ACCEL,1USAANL) Argonne National Laboratory fast 1075700100007 neutron generator 1075700100008 STATUS (APRVD) Approved by D.L. Smith, 1979/4/30. 1075700100009 (TABLE) Data taken from tables in report. 1075700100010 HISTORY (19781227C) 1075700100011 (20091112A) VM:Updated to new date formats,lower case. 1075700100012 BIB updates. 1075700100013 ENDBIB 11 0 1075700100014 NOCOMMON 0 0 1075700100015 ENDSUBENT 14 0 1075700199999 SUBENT 10757002 20100322 13601075700200001 BIB 10 43 1075700200002 REACTION 1((82-PB-204(N,INL)82-PB-204-M,,SIG)/ 1075700200003 (92-U-238(N,F),,SIG)) 1075700200004 2(82-PB-204(N,INL)82-PB-204-M,,SIG) 1075700200005 DECAY-DATA (82-PB-204-M,66.9MIN,DG) 1075700200006 SAMPLE 2.544-Cm diameter, 0.188-cm thick natural lead. 1075700200007 INC-SOURCE (P-LI7) Protons on 7Li for energies less than 5-MeV. 1075700200008 (D-D) Deuterons on deuterium for energies 5-10 MeV. 1075700200009 DETECTOR (GELI) True coaxial geli detector. 1075700200010 Calibrated with activated 204(m)Pb source and coin- 1075700200011 cidence counting. 1075700200012 (IOCH) Ionization chamber, steel can with wall thick- 1075700200013 ness of 0.025-cm and filled with methane at 1-atm. 1075700200014 MONITOR 2(92-U-238(N,F),,SIG) Cross sections from ENDF/B-IV. 1075700200015 METHOD Sample attached to outside of ionization chamber. Uran-1075700200016 ium monitor placed inside can, adjacent to sample. 1075700200017 Noise and alpha pulses eliminated by discriminator. 1075700200018 CORRECTION Raw sample counts corrected for: 1075700200019 .decay half life and other time factors, 1075700200020 .sum coincidences, 1075700200021 .gamma absorption, 1075700200022 .geometrical factors, 1075700200023 .internal conversion properties of 204(m)Pb, 1075700200024 .effects of neutron absorption and scattering. 1075700200025 Raw fission counts corrected for: 1075700200026 .deposit thickness effects, 1075700200027 .rejection of low pulse height events by discriminator,1075700200028 .geometric factors, 1075700200029 .effects of neutron absorption and scattering, 1075700200030 .fissions produced by neutrons from target assembly. 1075700200031 ERR-ANALYS1(ERR-T) Statistical uncertainty combined in quadrature 1075700200032 with systematic uncertainties (~7%). 1075700200033 Sources of systematic error include: 1075700200034 (ERR-1) gamma detector efficiency, 1075700200035 (ERR-2,,1.) decay half life effects, 1075700200036 (ERR-3) geometry, 1075700200037 (ERR-4) neutron source properties, 1075700200038 (ERR-5,,1.) scattering corrections, 1075700200039 (ERR-6) mass of uranium deposit, 1075700200040 (ERR-7) number of 204Pb atoms in sample, 1075700200041 (ERR-8) miscellaneous errors. 1075700200042 2No uncertainties given. 1075700200043 HISTORY (19830607A) Added DECAY-DATA, removed COMMON. 1075700200044 (20100322A) Error coding updated. 1075700200045 ENDBIB 43 0 1075700200046 COMMON 6 3 1075700200047 ERR-1 ERR-3 ERR-4 ERR-6 ERR-7 ERR-8 1075700200048 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1075700200049 6. 2. 2. 1. 2. 1. 1075700200050 ENDCOMMON 3 0 1075700200051 DATA 5 51 1075700200052 EN EN-RSL DATA 1ERR-T 1DATA 2 1075700200053 MEV MEV NO-DIM PER-CENT B 1075700200054 2.631 0.124 1.212 E-02 9.9 6.639 E-03 1075700200055 2.690 0.125 1.777 E-02 9.0 9.730 E-03 1075700200056 2.740 0.126 2.092 E-02 8.6 1.145 E-02 1075700200057 2.790 0.126 2.389 E-02 8.3 1.307 E-02 1075700200058 2.842 0.127 2.434 E-02 9.0 1.331 E-02 1075700200059 2.891 0.127 3.242 E-02 8.0 1.772 E-02 1075700200060 2.941 0.128 2.881 E-02 9.0 1.574 E-02 1075700200061 2.991 0.129 3.863 E-02 7.8 2.110 E-02 1075700200062 3.041 0.129 4.137 E-02 8.0 2.259 E-02 1075700200063 3.091 0.130 4.826 E-02 7.8 2.634 E-02 1075700200064 3.141 0.131 4.778 E-02 7.8 2.607 E-02 1075700200065 3.203 0.108 5.688 E-02 7.6 3.102 E-02 1075700200066 3.241 0.132 5.662 E-02 7.8 3.087 E-02 1075700200067 3.291 0.133 6.028 E-02 7.8 3.285 E-02 1075700200068 3.345 0.111 6.359 E-02 7.6 3.476 E-02 1075700200069 3.380 0.154 6.627 E-02 7.6 3.631 E-02 1075700200070 3.388 0.134 6.501 E-02 7.6 3.564 E-02 1075700200071 3.437 0.154 6.730 E-02 7.5 3.701 E-02 1075700200072 3.480 0.154 6.902 E-02 7.9 3.806 E-02 1075700200073 3.585 0.154 8.018 E-02 8.1 4.443 E-02 1075700200074 3.677 0.154 8.519 E-02 7.5 4.758 E-02 1075700200075 3.778 0.154 9.027 E-02 7.5 5.074 E-02 1075700200076 3.878 0.155 9.547 E-02 7.5 5.399 E-02 1075700200077 3.979 0.155 0.1069 7.5 6.088 E-02 1075700200078 3.998 0.143 0.1068 7.5 6.087 E-02 1075700200079 4.097 0.145 0.1146 7.6 6.520 E-02 1075700200080 4.198 0.146 0.1198 7.6 6.802 E-02 1075700200081 4.298 0.148 0.1260 7.6 7.134 E-02 1075700200082 4.404 0.150 0.1327 7.6 7.499 E-02 1075700200083 4.503 0.151 0.1405 7.7 7.922 E-02 1075700200084 4.603 0.153 0.1430 7.5 8.048 E-02 1075700200085 4.703 0.154 0.1578 7.7 8.861 E-02 1075700200086 4.804 0.156 0.1664 7.6 9.323 E-02 1075700200087 4.903 0.158 0.1643 7.7 9.187 E-02 1075700200088 5.004 0.159 0.1718 7.7 9.589 E-02 1075700200089 5.103 0.161 0.1587 7.9 8.835 E-02 1075700200090 5.105 0.309 0.1834 7.6 0.1021 1075700200091 5.201 0.163 0.1727 7.8 9.593 E-02 1075700200092 5.301 0.164 0.1877 7.8 0.1047 1075700200093 5.456 0.291 0.1941 7.6 0.1099 1075700200094 5.867 0.278 0.2005 7.5 0.1248 1075700200095 6.414 0.270 0.1888 7.7 0.1522 1075700200096 6.424 0.331 0.1821 8.0 0.1474 1075700200097 6.934 0.269 0.2103 7.7 0.1709 1075700200098 7.443 0.273 0.1992 7.5 0.1927 1075700200099 7.945 0.279 0.2290 7.4 0.2266 1075700200100 8.439 0.287 0.2443 7.5 0.2414 1075700200101 8.930 0.296 0.2722 7.4 0.2686 1075700200102 9.434 0.307 0.2763 7.4 0.2722 1075700200103 9.438 0.420 0.2341 7.5 0.2306 1075700200104 9.903 0.318 0.2665 7.4 0.2602 1075700200105 ENDDATA 53 0 1075700200106 ENDSUBENT 105 0 1075700299999 SUBENT 10757003 20100322 13601075700300001 BIB 10 46 1075700300002 REACTION 1((82-PB-204(N,INL)82-PB-204-M,,SIG)/ 1075700300003 (92-U-235(N,F),,SIG)) 1075700300004 2(82-PB-204(N,INL)82-PB-204-M,,SIG) 1075700300005 SAMPLE 204Pb enriched to 99.73%, 9.569-gms, 2.544-cm 1075700300006 diameter, 0.17-cm thick. 1075700300007 DECAY-DATA (82-PB-204-M,66.9MIN,DG) 1075700300008 MONITOR 2(92-U-235(N,F),,SIG) From ENDF/B-IV. 1075700300009 INC-SOURCE (P-LI7) Protons on 7Li for energies less than 5-MeV. 1075700300010 (D-D) Deuterons on deuterium for energies 5-10 MeV. 1075700300011 DETECTOR (GELI) True coaxial geli detector. 1075700300012 Calibrated with activated 204Pb source and coin- 1075700300013 cidence counting. 1075700300014 (IOCH) Ionization chamber, steel can with wall thick- 1075700300015 ness of 0.025-cm and filled with methane at 1-atm. 1075700300016 METHOD Sample attached to outside of ionization chamber. Uran-1075700300017 ium monitor placed inside can, adjacent to sample. 1075700300018 Noise and alpha pulses eliminated by discriminator. 1075700300019 Activity of 204(m)Pb allowed to decay 24 hours between1075700300020 irradiations. 1075700300021 CORRECTION Raw sample counts corrected for: 1075700300022 .decay half life and other time factors, 1075700300023 .sum coincidences, 1075700300024 .gamma absorption, 1075700300025 .geometrical factors, 1075700300026 .internal conversion properties of 204(m)Pb, 1075700300027 .effects of neutron absorption and scattering. 1075700300028 Raw fission counts corrected for: 1075700300029 .deposit thickness effects, 1075700300030 .rejection of low pulse height events by discriminator,1075700300031 .geometric factors, 1075700300032 .effects of neutron absorption and scattering, 1075700300033 .fissions produced by neutrons from target assembly, 1075700300034 .thermal background. 1075700300035 ERR-ANALYS1(ERR-T) Statistical uncertainty combined in quadrature 1075700300036 with systematic uncertainties (~7%). 1075700300037 Sources of systematic error include: 1075700300038 (ERR-1) gamma detector efficiency, 1075700300039 (ERR-2,,1.) decay half life effects, 1075700300040 (ERR-3) geometry, 1075700300041 (ERR-4) neutron source properties, 1075700300042 (ERR-5,,1.) scattering corrections, 1075700300043 (ERR-6) mass of uranium deposit, 1075700300044 (ERR-7) miscellaneous errors. 1075700300045 2No uncertainties given. 1075700300046 HISTORY (19830607A) Added decay-data, removed common. 1075700300047 (20100322A) Error coding updated. 1075700300048 ENDBIB 46 0 1075700300049 COMMON 5 3 1075700300050 ERR-1 ERR-3 ERR-4 ERR-6 ERR-7 1075700300051 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1075700300052 6. 2. 2. 1. 1. 1075700300053 ENDCOMMON 3 0 1075700300054 DATA 5 4 1075700300055 EN EN-RSL DATA 1ERR-T 1DATA 2 1075700300056 MEV MEV NO-DIM PER-CENT B 1075700300057 2.220 0.065 1.646 E-05 55.4 2.100 E-05 1075700300058 2.424 0.068 4.878 E-04 10.4 6.244 E-04 1075700300059 2.520 0.069 3.473 E-03 7.4 4.446 E-03 1075700300060 2.619 0.071 5.483 E-03 7.7 6.969 E-03 1075700300061 ENDDATA 6 0 1075700300062 ENDSUBENT 61 0 1075700399999 SUBENT 10757004 20100322 13601075700400001 BIB 10 46 1075700400002 REACTION 1((82-PB-204(N,INL)82-PB-204-M,,SIG)/ 1075700400003 (92-U-238(N,F),,SIG)) 1075700400004 2(82-PB-204(N,INL)82-PB-204-M,,SIG) 1075700400005 SAMPLE 204Pb enriched to 99.73%, 9.569-gms, 2.544-cm 1075700400006 diameter, 0.17-cm thick. 1075700400007 DECAY-DATA (82-PB-204-M,66.9MIN,DG) 1075700400008 MONITOR 2(92-U-238(N,F),,SIG) From ENDF-B/IV 1075700400009 INC-SOURCE (P-LI7) Protons on 7Li for energies less than 5-MeV. 1075700400010 (D-D) Deuterons on deuterium for energies 5-10 MeV. 1075700400011 DETECTOR (GELI) True coaxial geli detector. 1075700400012 Calibrated with activated Pb-204 source and coin- 1075700400013 cidence counting. 1075700400014 (IOCH) Ionization chamber, steel can with wall thick- 1075700400015 ness of 0.025-cm and filled with methane at 1-atm. 1075700400016 METHOD Sample attached to outside of ionization chamber. Uran-1075700400017 ium monitors placed inside can, adjacent to sample. 1075700400018 Noise and alpha pulses eliminated by discriminator. 1075700400019 Activity of Pb-204-m allowed to decay 24 hours between 1075700400020 irradiations. 1075700400021 CORRECTION Raw sample counts corrected for: 1075700400022 .decay half life and other time factors, 1075700400023 .sum coincidences, 1075700400024 .gamma absorption, 1075700400025 .geometrical factors, 1075700400026 .internal conversion properties of 204(m)Pb, 1075700400027 .effects of neutron absorption and scattering. 1075700400028 Raw fission counts corrected for: 1075700400029 .deposit thickness effects, 1075700400030 .rejection of low pulse height events by discriminator,1075700400031 .geometric factors, 1075700400032 .effects of neutron absorption and scattering, 1075700400033 .monitor fissions produced by neutrons from target 1075700400034 assembly. 1075700400035 ERR-ANALYS1(ERR-T) Statistical uncertainty combined in quadrature 1075700400036 with systematic uncertainties (~7%). 1075700400037 Sources of systematic error include: 1075700400038 (ERR-1) gamma detector efficiency, 1075700400039 (ERR-2,,1.) decay half life effects, 1075700400040 (ERR-3) geometry, 1075700400041 (ERR-4) neutron source properties, 1075700400042 (ERR-5,,1.) scattering corrections, 1075700400043 (ERR-6) mass of uranium deposit, 1075700400044 (ERR-7) miscellaneous errors. 1075700400045 2No uncertainties given. 1075700400046 HISTORY (19830607A) Added decay-data, removed common. 1075700400047 (20091112A) Error coding updated. 1075700400048 ENDBIB 46 0 1075700400049 COMMON 5 3 1075700400050 ERR-1 ERR-3 ERR-4 ERR-6 ERR-7 1075700400051 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1075700400052 6. 2. 2. 1. 1. 1075700400053 ENDCOMMON 3 0 1075700400054 DATA 5 10 1075700400055 EN EN-RSL DATA 1ERR-T 1DATA 2 1075700400056 MEV MEV NO-DIM PER-CENT B 1075700400057 2.348 0.061 3.143 E-04 21.2 1.725 E-04 1075700400058 2.390 0.065 4.663 E-04 11.1 2.558 E-04 1075700400059 2.488 0.083 3.833 E-03 7.7 2.101 E-03 1075700400060 2.585 0.097 1.129 E-02 7.3 6.187 E-03 1075700400061 2.628 0.088 1.236 E-02 7.3 6.770 E-03 1075700400062 2.736 0.089 1.785 E-02 7.2 9.765 E-03 1075700400063 2.959 0.153 4.140 E-02 7.0 2.262 E-02 1075700400064 3.437 0.153 6.736 E-02 7.6 3.704 E-02 1075700400065 4.062 0.155 1.118 E-01 7.0 6.363 E-02 1075700400066 4.903 0.157 1.648 E-01 7.0 9.216 E-02 1075700400067 ENDDATA 12 0 1075700400068 ENDSUBENT 67 0 1075700499999 SUBENT 10757005 20100322 13601075700500001 BIB 10 44 1075700500002 REACTION 1((82-PB-204(N,INL)82-PB-204-M,,SIG)/ 1075700500003 (92-U-235(N,F),,SIG)) 1075700500004 2(82-PB-204(N,INL)82-PB-204-M,,SIG) 1075700500005 SAMPLE 2.544-cm diameter, 0.188-cm thick natural lead. 1075700500006 DECAY-DATA (82-PB-204-M,66.9MIN,DG) 1075700500007 INC-SOURCE (P-LI7) Protons on 7Li. 1075700500008 DETECTOR (GELI) True coaxial geli detector 1075700500009 calibrated with activated Pb-204 source and coin- 1075700500010 cidence counting. 1075700500011 (IOCH) Ionization chamber, steel can with wall thick- 1075700500012 ness of 0.025-cm and filled with methane at 1-atm. 1075700500013 MONITOR 2(92-U-235(N,F),,SIG) Cross sections from ENDF/B-IV. 1075700500014 METHOD Sample attached to outside of ionization chamber. Uran-1075700500015 ium monitors placed inside can, adjacent to sample. 1075700500016 Noise and alpha pulses eliminated by discriminator. 1075700500017 CORRECTION Raw sample counts corrected for: 1075700500018 .decay half life and other time factors, 1075700500019 .sum coincidences, 1075700500020 .gamma absorption, 1075700500021 .geometrical factors, 1075700500022 .internal conversion properties of 204(m)Pb, 1075700500023 .effects of neutron absorption and scattering. 1075700500024 Raw fission counts corrected for: 1075700500025 .deposit thickness effects, 1075700500026 .rejection of low pulse height events by discriminator,1075700500027 .geometric factors, 1075700500028 .effects of neutron absorption and scattering, 1075700500029 .monitor fissions produced by neutrons from target 1075700500030 assembly, 1075700500031 .thermal background. 1075700500032 ERR-ANALYS1(ERR-T) Statistical uncertainty combined in quadrature 1075700500033 with systematic uncertainties (~7%). 1075700500034 Sources of systematic error include: 1075700500035 (ERR-1) gamma detector efficiency, 1075700500036 (ERR-2,,1.) decay half life effects, 1075700500037 (ERR-3) geometry, 1075700500038 (ERR-4) neutron source properties, 1075700500039 (ERR-5,,1.) scattering corrections, 1075700500040 (ERR-6) mass of uranium deposit, 1075700500041 (ERR-7) number of 204Pb atoms in sample, 1075700500042 (ERR-8) miscellaneous errors. 1075700500043 2No uncertainties given. 1075700500044 HISTORY (19830607A) Added decay-data, removed common. 1075700500045 (20100322A) Error coding updated. 1075700500046 ENDBIB 44 0 1075700500047 COMMON 6 3 1075700500048 ERR-1 ERR-3 ERR-4 ERR-6 ERR-7 ERR-8 1075700500049 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1075700500050 6. 2. 2. 1. 2. 1. 1075700500051 ENDCOMMON 3 0 1075700500052 DATA 5 8 1075700500053 EN EN-RSL DATA 1ERR-T 1DATA 2 1075700500054 MEV MEV NO-DIM PER-CENT B 1075700500055 3.368 0.114 0.03191 7.6 0.03832 1075700500056 3.468 0.115 0.03400 7.6 0.04053 1075700500057 3.573 0.116 0.03729 7.9 0.04411 1075700500058 3.664 0.117 0.04232 7.8 0.04973 1075700500059 3.763 0.118 0.04634 7.6 0.05399 1075700500060 3.861 0.119 0.04920 7.7 0.05688 1075700500061 3.955 0.150 0.04731 7.4 0.05426 1075700500062 3.960 0.120 0.05324 7.8 0.06107 1075700500063 ENDDATA 10 0 1075700500064 ENDSUBENT 63 0 1075700599999 SUBENT 10757006 20100322 13601075700600001 BIB 11 38 1075700600002 REACTION 1((82-PB-204(N,INL)82-PB-204,PAR,DA,G,4PI)/ 1075700600003 (92-U-235(N,F),,SIG)) 1075700600004 2(82-PB-204(N,INL)82-PB-204,PAR,DA,G,4PI) 1075700600005 SAMPLE 204Pb enriched to 99.73%, 9.569-gms, 2.544-cm 1075700600006 diameter, 0.17-cm thick. 1075700600007 INC-SOURCE (P-LI7) Protons on 7Li. 1075700600008 DETECTOR (GELI) True coaxial detector for gammas 1075700600009 calibrated with NBS standard sources. 1075700600010 Fission detector, 2.54-cm deposit of 2.523E18 atoms 1075700600011 of uranium, 93.3% 235U, for neutron flux. 1075700600012 (LONGC,SCIN) BF3 long counter, small plastic 1075700600013 scintillator and beam current integrator used to 1075700600014 check fission detector. 1075700600015 MONITOR 2(92-U-235(N,F),,SIG) From ENDF/B-IV. 1075700600016 METHOD (TOF). Axis of sample coincident with beam axis. 1075700600017 Fission detector placed between neutron 1075700600018 source and sample, each being irradiated separately 1075700600019 due to small sample size. Distances between neutron 1075700600020 source and the sample and fission detector measured 1075700600021 with micrometer to insure accurate calibration. 1075700600022 ANALYSIS (4PI1A) 1075700600023 CORRECTION Corrected for background, geometry, secondary neutron 1075700600024 groups from source reaction, lithium target thickness,1075700600025 absorption and scattering of neutrons and gammas, and 1075700600026 thermal neutron fissions. 1075700600027 ERR-ANALYS (DATA-ERR) Includes gamma yield uncertainty combined 1075700600028 with overall systematic uncertainty (~6%). 235U 1075700600029 fission uncertainty is not included. 1075700600030 Systematic errors include: 1075700600031 (ERR-1) gamma detector efficiency 1075700600032 (ERR-2) geometry 1075700600033 (ERR-3) neutron source properties 1075700600034 (ERR-4,0.5,3.) gamma absorption and scattering 1075700600035 (ERR-5) mass of uranium deposit 1075700600036 (ERR-6,,2.) neutron absorption and scattering 1075700600037 STATUS Data has been increased by 4.5% over published 1075700600038 values due to revision in normalization by author. 1075700600039 HISTORY (20100322A) Error coding updated. Reaction 1 corrected.1075700600040 ENDBIB 38 0 1075700600041 COMMON 5 3 1075700600042 ANG ERR-1 ERR-2 ERR-3 ERR-5 1075700600043 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 1075700600044 125. 4. 3. 2. 1. 1075700600045 ENDCOMMON 3 0 1075700600046 DATA 6 133 1075700600047 E EN EN-RSL DATA 1DATA-ERR 1DATA 21075700600048 MEV MEV MEV NO-DIM PER-CENT B 1075700600049 0.2894 1.942 0.123 0.08309 25.7 0.1054 1075700600050 0.2894 1.992 0.122 0.07454 20.9 0.09467 1075700600051 0.2894 2.042 0.120 0.1145 25.7 0.1456 1075700600052 0.2894 2.142 0.118 0.1259 25.7 0.1604 1075700600053 0.2894 2.242 0.116 0.1894 25.7 0.2416 1075700600054 0.2894 2.344 0.114 0.1411 30.6 0.1803 1075700600055 0.2894 2.444 0.112 0.1133 30.6 0.1452 1075700600056 0.2894 2.495 0.111 0.1275 16.2 0.1634 1075700600057 0.2894 2.546 0.110 0.1409 30.6 0.1799 1075700600058 0.2894 2.746 0.106 0.10400 30.6 0.1309 1075700600059 0.2894 2.849 0.105 0.1641 20.9 0.2051 1075700600060 0.2894 2.949 0.103 0.1095 25.7 0.1359 1075700600061 0.2894 2.999 0.102 0.1317 11.7 0.1627 1075700600062 0.3307 1.837 0.125 0.09691 20.9 0.1228 1075700600063 0.3307 1.989 0.122 0.04039 25.7 0.05130 1075700600064 0.3307 2.444 0.112 0.1003 30.6 0.1285 1075700600065 0.3307 2.495 0.111 0.07934 25.7 0.1017 1075700600066 0.3307 2.546 0.110 0.09361 25.7 0.1195 1075700600067 0.3307 2.999 0.102 0.04659 30.6 0.05758 1075700600068 0.3618 2.949 0.103 0.07780 30.6 0.09647 1075700600069 0.3618 2.999 0.102 0.04916 30.6 0.06076 1075700600070 0.3750 1.990 0.122 0.07971 20.9 0.10123 1075700600071 0.3750 2.040 0.120 0.08658 20.9 0.1100 1075700600072 0.3750 2.242 0.116 0.1194 25.7 0.1524 1075700600073 0.3750 2.495 0.111 0.06707 25.7 0.08598 1075700600074 0.3750 2.646 0.108 0.06365 30.6 0.08071 1075700600075 0.3750 2.949 0.103 0.09936 25.7 0.1232 1075700600076 0.3750 2.999 0.102 0.06891 20.9 0.08517 1075700600077 0.4518 1.838 0.125 0.10425 25.7 0.1321 1075700600078 0.4518 1.990 0.122 0.07522 20.9 0.09552 1075700600079 0.4518 2.343 0.114 0.06633 30.6 0.08477 1075700600080 0.4518 2.495 0.111 0.07528 20.9 0.09651 1075700600081 0.4518 2.849 0.105 0.08903 25.7 0.1113 1075700600082 0.4518 2.949 0.103 0.1045 25.7 0.1296 1075700600083 0.4518 2.999 0.102 0.06409 16.2 0.07922 1075700600084 0.6841 1.745 0.128 0.1713 25.7 0.2166 1075700600085 0.6841 1.839 0.125 0.1277 20.9 0.1618 1075700600086 0.6841 1.940 0.123 0.1279 20.9 0.1623 1075700600087 0.6841 1.990 0.122 0.1190 16.2 0.1511 1075700600088 0.6841 2.041 0.120 0.1683 20.9 0.2140 1075700600089 0.6841 2.141 0.118 0.1486 25.7 0.1892 1075700600090 0.6841 2.242 0.116 0.1722 25.7 0.2198 1075700600091 0.6841 2.343 0.114 0.1415 25.7 0.1809 1075700600092 0.6841 2.444 0.112 0.2239 20.9 0.2869 1075700600093 0.6841 2.495 0.111 0.1666 11.7 0.2136 1075700600094 0.6841 2.546 0.110 0.1711 20.9 0.2185 1075700600095 0.6841 2.647 0.108 0.1549 25.7 0.1964 1075700600096 0.6841 2.747 0.106 0.1938 20.9 0.2440 1075700600097 0.6841 2.849 0.105 0.2237 20.9 0.2796 1075700600098 0.6841 2.949 0.103 0.2069 20.9 0.2565 1075700600099 0.6841 2.999 0.102 0.1702 7.8 0.2104 1075700600100 0.7059 1.736 0.128 0.06320 30.6 0.07995 1075700600101 0.7059 2.242 0.116 0.08542 30.6 0.1090 1075700600102 0.7059 2.647 0.108 0.1147 30.6 0.1455 1075700600103 0.7059 2.949 0.103 0.08478 30.6 0.1051 1075700600104 0.7059 2.999 0.102 0.09309 11.7 0.1151 1075700600105 0.7660 1.945 0.123 0.08366 25.7 0.1062 1075700600106 0.7660 1.993 0.122 0.04545 20.9 0.05772 1075700600107 0.7660 2.496 0.111 0.06757 16.2 0.08663 1075700600108 0.7660 2.849 0.105 0.1235 25.7 0.1545 1075700600109 0.7660 2.949 0.103 0.10155 30.6 0.1259 1075700600110 0.7660 2.999 0.102 0.07867 11.7 0.09723 1075700600111 0.7822 1.989 0.122 0.06098 20.9 0.07743 1075700600112 0.7822 2.495 0.111 0.04983 20.9 0.06387 1075700600113 0.7822 2.949 0.103 0.07679 30.6 0.09522 1075700600114 0.7822 2.999 0.102 0.06480 16.2 0.08009 1075700600115 0.8994 0.967 0.159 0.2808 16.2 0.3355 1075700600116 0.8994 1.001 0.156 0.2002 11.7 0.2421 1075700600117 0.8994 1.037 0.154 0.2787 13.4 0.3411 1075700600118 0.8994 1.130 0.149 0.3716 11.7 0.4648 1075700600119 0.8994 1.230 0.145 0.4178 11.7 0.5234 1075700600120 0.8994 1.331 0.141 0.4472 11.7 0.5612 1075700600121 0.8994 1.432 0.138 0.4551 11.7 0.5726 1075700600122 0.8994 1.483 0.136 0.4775 7.8 0.6011 1075700600123 0.8994 1.534 0.134 0.4898 11.7 0.6172 1075700600124 0.8994 1.635 0.131 0.5586 11.7 0.7050 1075700600125 0.8994 1.736 0.128 0.5476 10. 0.6926 1075700600126 0.8994 1.837 0.125 0.6440 10. 0.8160 1075700600127 0.8994 1.939 0.123 0.6957 10. 0.8828 1075700600128 0.8994 1.990 0.122 0.6849 7.8 0.8699 1075700600129 0.8994 2.041 0.120 0.7168 10. 0.9110 1075700600130 0.8994 2.141 0.118 0.6577 11.7 0.8379 1075700600131 0.8994 2.242 0.116 0.7603 11.7 0.9702 1075700600132 0.8994 2.343 0.114 0.8479 11.7 1.084 1075700600133 0.8994 2.444 0.112 0.8492 10. 1.088 1075700600134 0.8994 2.496 0.111 0.8098 7.8 1.038 1075700600135 0.8994 2.546 0.110 0.8912 10. 1.138 1075700600136 0.8994 2.647 0.108 0.9543 10. 1.210 1075700600137 0.8994 2.747 0.106 0.9512 10. 1.198 1075700600138 0.8994 2.849 0.105 1.007 7.8 1.258 1075700600139 0.8994 2.949 0.103 1.060 7.8 1.314 1075700600140 0.8994 2.999 0.102 0.9605 7.8 1.187 1075700600141 0.9187 2.243 0.116 0.1055 25.7 0.1347 1075700600142 0.9187 2.495 0.111 0.07260 16.2 0.09307 1075700600143 0.9187 2.647 0.108 0.1051 25.7 0.1332 1075700600144 0.9187 2.747 0.106 0.08194 25.7 0.10316 1075700600145 0.9187 2.849 0.105 0.1130 25.7 0.1412 1075700600146 0.9187 2.949 0.103 0.1172 25.7 0.1454 1075700600147 0.9187 2.999 0.102 0.06197 16.2 0.07659 1075700600148 0.9839 2.649 0.108 0.1067 25.7 0.1352 1075700600149 0.9839 2.748 0.106 0.09520 20.9 0.1199 1075700600150 0.9839 2.850 0.105 0.1436 20.9 0.1794 1075700600151 0.9839 2.950 0.103 0.1469 20.9 0.1821 1075700600152 0.9839 3.000 0.102 0.1515 11.7 0.1873 1075700600153 1.0617 2.999 0.102 0.06975 16.2 0.08621 1075700600154 1.3514 1.499 0.136 0.1001 16.2 0.1261 1075700600155 1.3514 1.543 0.134 0.1771 20.9 0.2232 1075700600156 1.3514 1.638 0.131 0.1490 20.9 0.1881 1075700600157 1.3514 1.738 0.128 0.1427 20.9 0.1806 1075700600158 1.3514 1.838 0.125 0.2025 16.2 0.2565 1075700600159 1.3514 1.940 0.123 0.1784 20.9 0.2263 1075700600160 1.3514 1.990 0.122 0.1913 11.7 0.2430 1075700600161 1.3514 2.040 0.120 0.1831 20.9 0.2327 1075700600162 1.3514 2.141 0.118 0.1814 20.9 0.2312 1075700600163 1.3514 2.242 0.116 0.1940 20.9 0.2475 1075700600164 1.3514 2.343 0.114 0.2037 20.9 0.2603 1075700600165 1.3514 2.445 0.112 0.2170 20.9 0.2780 1075700600166 1.3514 2.496 0.111 0.2109 11.7 0.2703 1075700600167 1.3514 2.546 0.110 0.2256 20.9 0.2881 1075700600168 1.3514 2.647 0.108 0.2406 20.9 0.3050 1075700600169 1.3514 2.747 0.106 0.2678 16.2 0.3372 1075700600170 1.3514 2.849 0.105 0.2785 16.2 0.3481 1075700600171 1.3514 2.949 0.103 0.2537 16.2 0.3146 1075700600172 1.3514 2.999 0.102 0.2772 7.8 0.3427 1075700600173 1.6663 2.999 0.102 0.06347 20.9 0.07845 1075700600174 1.6820 2.495 0.111 0.07002 20.9 0.08976 1075700600175 1.6820 2.999 0.102 0.05273 20.9 0.06518 1075700600176 1.7223 2.999 0.102 0.05706 20.9 0.07053 1075700600177 1.7619 2.495 0.111 0.04652 25.7 0.05965 1075700600178 1.7619 2.999 0.102 0.04253 25.7 0.05256 1075700600179 1.8732 2.949 0.103 0.08638 30.6 0.1071 1075700600180 1.8732 2.999 0.102 0.06682 20.9 0.08259 1075700600181 1.9341 2.999 0.102 0.03555 30.6 0.04394 1075700600182 ENDDATA 135 0 1075700600183 ENDSUBENT 182 0 1075700699999 SUBENT 10757007 20091113 13601075700700001 BIB 8 15 1075700700002 REACTION (82-PB-204(N,INL)82-PB-204,PAR,DA,G,RSD) 1075700700003 INC-SOURCE (P-LI7) Protons on 7Li. 1075700700004 SAMPLE 204Pb enriched to 99.73%, 9.569-gms, 2.544-cm 1075700700005 diameter, 0.17-cm thick. 1075700700006 DETECTOR (GELI) True coaxial detector for gammas 1075700700007 (LONGC) bf(3) long counter 1075700700008 (SCIN) small plastic scintillator 1075700700009 beam current integrator 1075700700010 latter two used as neutron beam monitors 1075700700011 MONITOR (92-U-235(N,F),,SIG) From ENDF/B-IV. 1075700700012 METHOD (TOF). 1075700700013 CORRECTION Corrected for background, geometry, secondary neutron 1075700700014 groups from source reaction, lithium target thickness,1075700700015 absorption and scattering of neutrons and gammas. 1075700700016 ERR-ANALYS (DATA-ERR) Includes only uncertainty in peak yield. 1075700700017 ENDBIB 15 0 1075700700018 COMMON 1 3 1075700700019 E 1075700700020 MEV 1075700700021 0.8994 1075700700022 ENDCOMMON 3 0 1075700700023 DATA 4 38 1075700700024 EN ANG DATA DATA-ERR 1075700700025 MEV ADEG NO-DIM NO-DIM 1075700700026 1.037 30. 1.830 0.275 1075700700027 1.037 40. 2.113 0.317 1075700700028 1.037 50. 1.392 0.279 1075700700029 1.037 60. 1.455 0.291 1075700700030 1.037 70. 0.715 0.178 1075700700031 1.037 80. 0.923 0.185 1075700700032 1.037 90. 1.094 0.219 1075700700033 1.037 90. 1.010 0.202 1075700700034 1.037 100. 1.134 0.170 1075700700035 1.037 110. 1.666 0.250 1075700700036 1.037 120. 1.467 0.220 1075700700037 1.037 130. 1.436 0.215 1075700700038 1.037 135. 1.601 0.240 1075700700039 1.230 30. 1.911 0.287 1075700700040 1.230 40. 1.564 0.156 1075700700041 1.230 50. 1.403 0.210 1075700700042 1.230 60. 1.193 0.239 1075700700043 1.230 70. 0.890 0.178 1075700700044 1.230 80. 1.060 0.159 1075700700045 1.230 90. 1.138 0.228 1075700700046 1.230 90. 0.987 0.197 1075700700047 1.230 100. 1.086 0.163 1075700700048 1.230 110. 1.300 0.195 1075700700049 1.230 120. 1.137 0.170 1075700700050 1.230 130. 1.510 0.151 1075700700051 1.230 135. 1.701 0.170 1075700700052 1.432 40. 1.313 0.131 1075700700053 1.432 50. 1.159 0.116 1075700700054 1.432 60. 1.207 0.121 1075700700055 1.432 70. 1.089 0.109 1075700700056 1.432 80. 0.845 0.127 1075700700057 1.432 90. 0.849 0.127 1075700700058 1.432 90. 1.053 0.105 1075700700059 1.432 100. 1.058 0.106 1075700700060 1.432 110. 1.174 0.117 1075700700061 1.432 120. 1.153 0.115 1075700700062 1.432 130. 1.063 0.106 1075700700063 1.432 135. 1.262 0.126 1075700700064 ENDDATA 40 0 1075700700065 ENDSUBENT 64 0 1075700799999 ENDENTRY 7 0 1075799999999