ENTRY 22865 20191103 22832286500000001 SUBENT 22865001 20191103 22832286500100001 BIB 5 13 2286500100002 TITLE Neutron capture cross section measurements of 129I, 2286500100003 133Cs and 141Pr with Linac time-of-flight measurements2286500100004 AUTHOR (K.Kobayashi,S.Lee,S.Yamamoto,M.Igashira,J.Yoon,T.Ro) 2286500100005 REFERENCE (C,2002BRUSS,,588,2002) Data for Pr-, Cs-133, I-129. 2286500100006 (J,NST,40,447,2003) Schemes,experimental details, 2286500100007 graphs,data for thermal neutrons on 141Pr 2286500100008 INSTITUTE (2JPNKTO) Lee, Yamamoto, Kobayashi 2286500100009 (3KORDAU) Yoon, Ro 2286500100010 HISTORY (20050129C) M.M. 2286500100011 (20171109U) SD: Ref. 2002BRUSS,588 as added. 2286500100012 (20191103A) SD: Subents 004, 005 added. Corrections 2286500100013 in all Subents. Title and authors corrected according 2286500100014 to the first ref. 2286500100015 ENDBIB 13 0 2286500100016 NOCOMMON 0 0 2286500100017 ENDSUBENT 16 0 2286500199999 SUBENT 22865002 20191103 22832286500200001 BIB 12 51 2286500200002 REACTION (59-PR-141(N,G)59-PR-142,,SIG) 2286500200003 FACILITY (LINAC,2JPNKTO) 46-MeV electron linear accelerator 2286500200004 at the Research Reactor Institute, Kyoto University 2286500200005 - KURRI. 2286500200006 METHOD (TOF) 12.7 m flight path in 135 degr. relative to 2286500200007 LINAC electron beam. 2286500200008 DETECTOR (BGO) 12 Bismuth germanate(Bi4-Ge3-O12)scintillators 2286500200009 (each of 5*5*7.5 cm3) assembly. 2286500200010 (BF3) BF3 proportional counter to monitor neutron beam 2286500200011 intensity. 2286500200012 MONITOR ((MONIT)5-B-10(N,A)3-LI-7,,SIG) To determine incident 2286500200013 neutron flux on sample in TOF method 2286500200014 (59-PR-141(N,G)59-PR-142,,SIG) 2286500200015 MONIT-REF (,S.F.Mughabghab+,B,NEUT.CS 1A,,,1981) 2286500200016 ANALYSIS For the high energy experiment in the energy range 2286500200017 0.7eV - 140 keV cross section was normalized to that 2286500200018 in the low energy region by integrating the respective2286500200019 data in the overlapped energy region from 0.7 to 3 eV 2286500200020 INC-SOURCE (PHOTO) 2286500200021 Photoneutron water-cooled tantalum target as pulsed 2286500200022 neutron source. 12 sheets of Ta of 5 cm diameter and 2286500200023 3 cm effective thickness. Collimation system: B4-C, 2286500200024 Pb, Li2-CO3, borated paraffin. 0.5 mm Cd sheet for 2286500200025 energy range above 0.7 eV. Energy calibration of 2286500200026 neutron beam was made by 4.92eV Au, 132.eV Co, 2286500200027 336.eV and 2.37keV Mn resonances 2286500200028 SAMPLE Pr foil : 99.9% purity, 2286500200029 1.609g/cm2, 7.658atom/kb, 3.0mm thickness, 2286500200030 1.27 cm in diameter. 2286500200031 boron powder of B-10 - 96.98% and B-11 - 3.02% 2286500200032 (packed in aluminium case of 0.1 mm thickness) : 2286500200033 99.999% purity, 2286500200034 0.872g/cm2, 52.42atom/kb, 8.0mm thickness, 2286500200035 1.8*1.8 cm2 dimensions. 2286500200036 graphite plate : 99.99% purity, 2286500200037 1.892g/cm2, 94.96atom/kb, 10.0mm thickness, 2286500200038 1.8*1.8 cm2 dimensions. 2286500200039 ERR-ANALYS (ERR-T) Total uncertainty 2286500200040 (ERR-S,1.1,220.) Statistical error 2286500200041 (ERR-1) Gamma-ray detection efficiency of BGO 2286500200042 (ERR-2) Deviation from 1/v-form in B-10(n,alpha) c-s 2286500200043 (ERR-3) Background subtraction 2286500200044 (ERR-4,1.0,1.5) Correction error for neutron 2286500200045 self-shielding and/or scattering effects 2286500200046 (ERR-5) Data normalization to monit1 2286500200047 (ERR-6) Given as 'delta-sigma' by the authors 2286500200048 STATUS (TABLE) Data are taken from table of authors 2286500200049 via internet 2286500200050 (DEP,22865003) Data were normalized by 2286500200051 activation method measured c-s at 0.0253 eV . 2286500200052 HISTORY (20191103A) SD: ERR-ANALYSIS corrected. STATUS updated.2286500200053 ENDBIB 51 0 2286500200054 COMMON 7 6 2286500200055 EN-NRM MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 2286500200056 ERR-5 2286500200057 EV B B PER-CENT PER-CENT PER-CENT 2286500200058 PER-CENT 2286500200059 0.0253 3.837 0.009 0.45 2.4 1.2286500200060 11.2 2286500200061 ENDCOMMON 6 0 2286500200062 DATA 4 143 2286500200063 EN DATA ERR-T ERR-6 2286500200064 EV B B B 2286500200065 3.940E-03 2.719E+01 3.586E+00 2.061E+00 2286500200066 5.630E-03 2.363E+01 2.852E+00 1.276E+00 2286500200067 8.050E-03 2.044E+01 2.364E+00 8.482E-01 2286500200068 1.150E-02 1.712E+01 1.949E+00 6.160E-01 2286500200069 1.643E-02 1.444E+01 1.630E+00 4.739E-01 2286500200070 2.348E-02 1.206E+01 1.355E+00 3.744E-01 2286500200071 3.356E-02 1.027E+01 1.151E+00 3.095E-01 2286500200072 4.797E-02 8.850E+00 9.912E-01 2.638E-01 2286500200073 6.856E-02 7.584E+00 8.500E-01 2.280E-01 2286500200074 9.798E-02 6.352E+00 7.143E-01 1.996E-01 2286500200075 1.400E-01 5.270E+00 6.004E-01 1.919E-01 2286500200076 2.001E-01 4.592E+00 5.453E-01 2.272E-01 2286500200077 2.861E-01 3.626E+00 4.566E-01 2.351E-01 2286500200078 4.088E-01 2.842E+00 3.727E-01 2.115E-01 2286500200079 5.843E-01 2.445E+00 3.300E-01 1.981E-01 2286500200080 8.351E-01 1.954E+00 2.785E-01 1.818E-01 2286500200081 1.194E+00 1.581E+00 2.396E-01 1.682E-01 2286500200082 1.706E+00 1.524E+00 2.308E-01 1.618E-01 2286500200083 2.438E+00 1.150E+00 1.879E-01 1.410E-01 2286500200084 3.485E+00 1.022E+00 1.741E-01 1.346E-01 2286500200085 4.166E+00 1.467E+00 1.819E-01 8.953E-02 2286500200086 4.981E+00 1.720E+00 2.416E-01 1.546E-01 2286500200087 5.954E+00 9.473E-01 1.865E-01 1.560E-01 2286500200088 7.876E+00 6.282E-01 1.233E-01 1.030E-01 2286500200089 1.126E+01 5.276E-01 1.094E-01 9.335E-02 2286500200090 1.609E+01 4.294E-01 9.725E-02 8.548E-02 2286500200091 2.300E+01 3.753E-01 8.922E-02 7.949E-02 2286500200092 3.287E+01 3.636E-01 8.453E-02 7.486E-02 2286500200093 4.507E+01 2.909E-01 7.520E-02 6.833E-02 2286500200094 5.337E+01 2.559E-01 7.401E-02 6.866E-02 2286500200095 6.068E+01 2.589E-01 7.791E-02 7.273E-02 2286500200096 7.254E+01 3.334E-01 8.292E-02 7.470E-02 2286500200097 8.144E+01 3.271E-01 1.229E-01 1.177E-01 2286500200098 8.453E+01 8.352E-01 2.522E-01 2.355E-01 2286500200099 8.538E+01 5.769E+00 1.274E+00 1.111E+00 2286500200100 8.581E+01 1.323E+01 1.738E+00 9.899E-01 2286500200101 8.624E+01 2.819E+01 3.510E+00 1.750E+00 2286500200102 8.735E+01 2.237E+01 2.562E+00 8.560E-01 2286500200103 8.892E+01 1.266E+00 2.868E-01 2.521E-01 2286500200104 9.203E+01 4.334E-01 1.120E-01 1.481E-01 2286500200105 1.037E+02 2.982E-01 7.053E-02 6.276E-02 2286500200106 1.239E+02 9.438E-01 1.282E-01 7.788E-02 2286500200107 1.482E+02 2.567E-01 5.316E-02 5.419E-02 2286500200108 1.996E+02 3.701E-01 7.004E-02 5.753E-02 2286500200109 2.051E+02 1.384E+00 1.872E-01 1.128E-01 2286500200110 2.108E+02 8.317E-01 9.962E-02 4.315E-02 2286500200111 2.185E+02 1.779E+01 2.020E+00 6.255E-01 2286500200112 2.247E+02 1.691E+01 1.959E+00 7.098E-01 2286500200113 2.275E+02 8.700E+00 1.096E+00 5.639E-01 2286500200114 2.294E+02 3.887E+00 5.479E-01 3.522E-01 2286500200115 2.382E+02 2.649E+01 3.044E+00 1.045E+00 2286500200116 2.422E+02 1.440E+01 1.662E+00 5.855E-01 2286500200117 2.453E+02 7.420E+00 9.336E-01 4.794E-01 2286500200118 2.474E+02 3.840E+00 5.322E-01 3.336E-01 2286500200119 2.506E+02 1.486E+00 2.252E-01 1.581E-01 2286500200120 2.573E+02 7.748E-01 1.273E-01 9.598E-02 2286500200121 2.690E+02 3.234E-01 6.080E-02 6.125E-02 2286500200122 2.868E+02 3.488E-01 7.076E-02 7.197E-02 2286500200123 3.140E+02 5.427E-01 1.044E-01 8.646E-02 2286500200124 3.356E+02 7.740E-01 1.769E-01 1.559E-01 2286500200125 3.441E+02 1.077E+00 1.953E-01 1.569E-01 2286500200126 3.494E+02 1.260E+00 2.057E-01 1.543E-01 2286500200127 3.640E+02 1.039E+01 1.255E+00 5.626E-01 2286500200128 3.679E+02 8.753E+00 1.070E+00 5.010E-01 2286500200129 3.717E+02 5.090E+00 6.679E-01 3.797E-01 2286500200130 3.757E+02 3.534E+00 5.056E-01 3.318E-01 2286500200131 3.797E+02 2.736E+00 4.219E-01 3.012E-01 2286500200132 3.837E+02 2.241E+00 3.695E-01 2.793E-01 2286500200133 3.878E+02 4.078E+00 5.874E-01 3.888E-01 2286500200134 3.986E+02 5.164E+00 6.161E-01 2.622E-01 2286500200135 4.095E+02 3.808E-01 1.931E-01 1.886E-01 2286500200136 4.141E+02 1.312E+00 2.835E-01 2.455E-01 2286500200137 4.259E+02 8.753E-01 1.572E-01 1.256E-01 2286500200138 4.457E+02 4.813E-01 1.195E-01 1.077E-01 2286500200139 4.641E+02 3.543E-01 1.289E-01 1.231E-01 2286500200140 4.809E+02 4.961E-01 1.541E-01 1.445E-01 2286500200141 4.986E+02 7.500E-01 1.373E-01 1.108E-01 2286500200142 5.237E+02 7.376E+00 9.178E-01 4.562E-01 2286500200143 5.303E+02 4.054E+00 5.621E-01 3.527E-01 2286500200144 5.475E+02 4.733E-01 1.265E-01 1.157E-01 2286500200145 5.846E+02 5.589E-01 1.075E-01 8.891E-02 2286500200146 6.506E+02 3.013E+00 3.897E-01 2.145E-01 2286500200147 6.643E+02 6.008E-01 1.831E-01 1.712E-01 2286500200148 6.786E+02 5.590E-01 1.529E-01 1.405E-01 2286500200149 7.403E+02 2.147E+00 3.020E-01 1.936E-01 2286500200150 7.627E+02 3.089E-01 1.294E-01 1.251E-01 2286500200151 7.862E+02 9.174E-01 1.934E-01 1.662E-01 2286500200152 8.108E+02 4.625E-01 8.542E-02 6.931E-02 2286500200153 8.565E+02 2.385E+00 3.428E-01 2.262E-01 2286500200154 8.703E+02 1.148E+00 2.195E-01 1.812E-01 2286500200155 8.845E+02 4.579E-01 1.664E-01 1.589E-01 2286500200156 9.065E+02 8.686E-01 1.775E-01 1.507E-01 2286500200157 9.291E+02 2.987E-01 1.032E-01 9.808E-02 2286500200158 9.607E+02 4.812E-01 9.893E-02 8.419E-02 2286500200159 9.771E+02 1.036E+00 1.958E-01 1.607E-01 2286500200160 9.940E+02 4.257E-01 1.346E-01 1.265E-01 2286500200161 1.011E+03 1.026E-01 6.895E-02 6.805E-02 2286500200162 1.038E+03 4.871E-01 1.528E-01 1.435E-01 2286500200163 1.076E+03 2.744E-01 1.236E-01 1.200E-01 2286500200164 1.105E+03 5.883E-01 1.428E-01 1.279E-01 2286500200165 1.125E+03 3.084E+00 4.574E-01 3.136E-01 2286500200166 1.146E+03 6.515E-01 1.907E-01 1.773E-01 2286500200167 1.179E+03 3.868E-01 1.267E-01 1.196E-01 2286500200168 1.236E+03 2.802E-01 1.004E-01 9.574E-02 2286500200169 1.297E+03 2.283E-01 1.219E-01 1.194E-01 2286500200170 1.336E+03 8.420E-01 2.510E-01 2.340E-01 2286500200171 1.363E+03 1.506E+00 2.999E-01 2.520E-01 2286500200172 1.390E+03 2.363E+00 3.681E-01 2.653E-01 2286500200173 1.419E+03 8.016E-01 2.531E-01 2.378E-01 2286500200174 1.511E+03 1.833E+00 3.081E-01 2.361E-01 2286500200175 1.560E+03 6.162E-01 1.529E-01 1.376E-01 2286500200176 1.647E+03 5.754E-02 1.255E-01 1.253E-01 2286500200177 1.684E+03 2.103E+00 3.534E-01 2.707E-01 2286500200178 1.743E+03 1.401E+00 2.302E-01 1.736E-01 2286500200179 1.803E+03 1.760E-01 1.279E-01 1.265E-01 2286500200180 1.868E+03 8.378E-01 1.781E-01 1.535E-01 2286500200181 1.935E+03 5.831E-01 2.160E-01 2.066E-01 2286500200182 1.982E+03 2.580E-01 2.106E-01 2.087E-01 2286500200183 2.031E+03 6.118E-01 2.183E-01 2.080E-01 2286500200184 2.163E+03 9.973E-01 1.832E-01 1.482E-01 2286500200185 2.276E+03 2.692E-01 1.112E-01 1.073E-01 2286500200186 2.367E+03 1.061E+00 2.549E-01 2.278E-01 2286500200187 2.465E+03 7.523E-01 1.703E-01 1.497E-01 2286500200188 2.567E+03 4.171E-01 2.115E-01 2.067E-01 2286500200189 2.678E+03 5.631E-01 1.634E-01 1.517E-01 2286500200190 2.793E+03 2.569E-01 1.919E-01 1.899E-01 2286500200191 3.051E+03 1.383E+00 2.631E-01 2.166E-01 2286500200192 3.195E+03 5.082E-01 1.365E-01 1.250E-01 2286500200193 3.401E+03 8.081E-01 1.659E-01 1.411E-01 2286500200194 3.628E+03 5.342E-01 1.176E-01 1.025E-01 2286500200195 3.879E+03 4.271E-01 1.231E-01 1.142E-01 2286500200196 4.156E+03 5.564E-01 1.561E-01 1.440E-01 2286500200197 4.552E+03 4.676E-01 1.150E-01 1.033E-01 2286500200198 5.589E+03 4.334E-01 8.172E-02 6.701E-02 2286500200199 7.011E+03 5.201E-01 1.039E-01 8.737E-02 2286500200200 8.495E+03 3.883E-01 8.101E-02 6.932E-02 2286500200201 1.051E+04 3.296E-01 7.587E-02 6.701E-02 2286500200202 1.333E+04 1.886E-01 4.484E-02 3.994E-02 2286500200203 1.920E+04 1.447E-01 3.034E-02 2.601E-02 2286500200204 3.253E+04 1.043E-01 2.261E-02 1.960E-02 2286500200205 5.523E+04 6.673E-02 1.810E-02 1.660E-02 2286500200206 9.016E+04 5.181E-02 1.619E-02 1.519E-02 2286500200207 1.390E+05 3.545E-02 1.417E-02 1.365E-02 2286500200208 ENDDATA 145 0 2286500200209 ENDSUBENT 208 0 2286500299999 SUBENT 22865003 20191103 22832286500300001 BIB 13 32 2286500300002 REACTION (59-PR-141(N,G)59-PR-142,,SIG) 2286500300003 METHOD (ACTIV) Irradiation time 30 min, 2286500300004 (STTA) Stack target irradiation 2286500300005 FACILITY (REAC,2JPNKTO) Heavy water thermal neutron facility 2286500300006 of Kyoto University reactor at 5 MW power. 2286500300007 DECAY-DATA (59-PR-142-G,19.13HR,DG,1576.,0.0370) 2286500300008 MONITOR ((MONIT)79-AU-197(N,G)79-AU-198,,SIG) 2286500300009 DECAY-MON (79-AU-198-G,2.694D,DG,412.,0.9558) 2286500300010 MONIT-REF (,S.F.Mughabghab+,B,NEUT.CS 1A,,,1981) 2286500300011 SAMPLE Pr foil : 99.9% purity, 2286500300012 0.088g/cm2, 0.376atom/kb, 0.1mm thickness, 2286500300013 1.0*1.0 cm2 dimensions. 2286500300014 Au foil : 99.9% purity, 2286500300015 0.047g/cm2, 0.144atom/kb, 0.05mm thickness, 2286500300016 0.95 cm in diameter. 2286500300017 INC-SPECT Leakage neutrons from heavy water tank as thermal 2286500300018 neutron source, having Maxwellian spectrum of 2286500300019 40 degrees Celcium neutron temperature. 2286500300020 DETECTOR (HPGE) 2286500300021 ERR-ANALYS (ERR-T) Total uncertainty 2286500300022 (ERR-S,0.8,1.0) Statistical error 2286500300023 (ERR-1) Gamma-ray detection efficiency of HPGe 2286500300024 (ERR-2) Number of atoms 2286500300025 (ERR-3) Geometrical factor for irradiation 2286500300026 (ERR-4) Correction for neutron self-shielding and/or 2286500300027 scattering effects 2286500300028 (ERR-5) Data normalization to MONIT 2286500300029 (ERR-6) Gamma-ray branching ratio for Pr-141(n,gamma) 2286500300030 reaction 2286500300031 STATUS (TABLE) From the abstract of Nucl.Sci.Tech.,40(2003)4472286500300032 HISTORY (20191103A) SD: ERR-ANALYSIS corrected. STATUS updated.2286500300033 SF8=MXW deleted from REACTION code. 2286500300034 ENDBIB 32 0 2286500300035 COMMON 8 6 2286500300036 MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 ERR-4 2286500300037 ERR-5 ERR-6 2286500300038 B B PER-CENT PER-CENT PER-CENT PER-CENT 2286500300039 PER-CENT PER-CENT 2286500300040 98.65 0.09 2.5 1.3 0.1 0.5 2286500300041 0.2 10.8 2286500300042 ENDCOMMON 6 0 2286500300043 DATA 4 1 2286500300044 EN DATA ERR-T ERR-T 2286500300045 EV B B PER-CENT 2286500300046 0.0253 11.6 1.3 11.2 2286500300047 ENDDATA 3 0 2286500300048 ENDSUBENT 47 0 2286500399999 SUBENT 22865004 20191103 22832286500400001 BIB 14 53 2286500400002 REACTION (55-CS-133(N,G)55-CS-134,,SIG) 2286500400003 FACILITY (LINAC,2JPNKTO) 46-MeV electron linear accelerator 2286500400004 at the Research Reactor Institute, Kyoto University 2286500400005 - KURRI. 2286500400006 METHOD (TOF) 12.7 m flight path in 135 degrees relative to 2286500400007 LINAC electron beam. 2286500400008 DETECTOR (BGO) 12 Bismuth germanate(Bi4-Ge3-O12)scintillators 2286500400009 (each of 5*5*7.5 cm3) assembly 2286500400010 (BF3) BF3 proportional counter to monitor neutron beam 2286500400011 intensity. 2286500400012 MONITOR (5-B-10(N,A)3-LI-7,,SIG) To determine incident 2286500400013 neutron flux on sample in TOF method 2286500400014 MONIT-REF (,S.F.Mughabghab+,B,NEUT.CS 1A,,,1981) 2286500400015 ANALYSIS For the high energy experiment in the energy range 2286500400016 0.7eV - 140 keV cross section was normalized to that 2286500400017 in the low energy region by integrating the respective2286500400018 data in the overlapped energy region from 0.7 to 3 eV 2286500400019 INC-SOURCE (PHOTO) 2286500400020 Photoneutron water-cooled tantalum target as pulsed 2286500400021 neutron source. 12 sheets of Ta of 5 cm diameter and 2286500400022 3 cm effective thickness. Collimation system: B4-C, 2286500400023 Pb, Li2-CO3, borated paraffin. 0.5 mm Cd sheet for 2286500400024 energy range above 0.7 eV. Energy calibration of 2286500400025 neutron beam was made by 4.92eV Au, 132.eV Co, 2286500400026 336.eV and 2.37keV Mn resonances 2286500400027 SAMPLE Cs2O powder : 99.% purity, 100.% isotop.composition; 2286500400028 0.552 g/cm2, 3.0 mm thickness, 2286500400029 1.8 x 1.8 cm2 in size. 2286500400030 boron powder of B-10 - 96.98% and B-11 - 3.02% 2286500400031 (packed in aluminium case of 0.1 mm thickness) : 2286500400032 99.999% purity, 2286500400033 0.872g/cm2, 8.0mm thickness, 2286500400034 1.8*1.8 cm2 dimensions. 2286500400035 graphite plate : 99.99% purity, 2286500400036 1.892g/cm2, 10.0mm thickness, 2286500400037 1.8*1.8 cm2 dimensions. 2286500400038 CORRECTION The effect of oxide in the Cs20 sample was corrected 2286500400039 by the calculation with the ENDF/B-VI data. 2286500400040 ERR-ANALYS (ERR-T,2.7,70.) Total uncertainty 2286500400041 (ERR-S,0.3,70.) Statistical error. Poor statistics are 2286500400042 observed in general in the cross section minimum 2286500400043 region, due to the low SIB ratio. 2286500400044 (ERR-1) Gamma-ray detection efficiency 2286500400045 (ERR-2) Deviation from 1/v-form in B-10(n,alpha) c-s 2286500400046 (ERR-3) correction error for neutron self-shielding 2286500400047 and/or scattering effects 2286500400048 COMMENT No any response from the author. Below 60 eV, two data2286500400049 sets presented in Subent 30842.002 and on fig.3 of this2286500400050 article are looked similar. Difference in the energy 2286500400051 range: on fig.3 upper energy limit is ~30 keV and in 2286500400052 Subent 30842.002 energy limit is 60 eV. 2286500400053 STATUS (UNOBT)Data presented on fig. 3 of 2002BRUSS,,588,2002 2286500400054 HISTORY (20191103C) SD 2286500400055 ENDBIB 53 0 2286500400056 COMMON 3 3 2286500400057 ERR-1 ERR-2 ERR-3 2286500400058 PER-CENT PER-CENT PER-CENT 2286500400059 0.45 2.4 1.1 2286500400060 ENDCOMMON 3 0 2286500400061 NODATA 0 0 2286500400062 ENDSUBENT 61 0 2286500499999 SUBENT 22865005 20191103 22832286500500001 BIB 13 56 2286500500002 REACTION (53-I-129(N,G)53-I-130,,SIG) 2286500500003 FACILITY (LINAC,2JPNKTO) 46-MeV electron linear accelerator 2286500500004 at the research reactor institute, Kyoto University 2286500500005 - KURRI. 2286500500006 METHOD (TOF) 12.7 M Flight path in 135 degrees relative to 2286500500007 LINAC electron beam. 2286500500008 DETECTOR (SCIN) C6D6 liquid scintillators (11 cm in diam. 2286500500009 and 5 cm thick) 2286500500010 (BF3) BF3 proportional counter to monitor neutron beam 2286500500011 intensity. 2286500500012 MONITOR (5-B-10(N,A)3-LI-7,,SIG) To determine incident 2286500500013 Neutron flux on sample in TOF method 2286500500014 MONIT-REF (,S.F.Mughabghab+,B,NEUT.CS 1A,,,1981) 2286500500015 ANALYSIS Since the counting rate data from the NaI-129 sample 2286500500016 practically include signals from 129I, Na and 127I 2286500500017 (impurity in the 129I sample), the effect of Nal-127 2286500500018 in the NaI-129 sample was subtracted first from the 2286500500019 NaI-129 data. 2286500500020 INC-SOURCE (PHOTO) 2286500500021 Photoneutron water-cooled tantalum target as pulsed 2286500500022 neutron source. 12 sheets of Ta of 5 cm diameter and 2286500500023 3 cm effective thickness. Collimation system: B4-C, 2286500500024 Pb, Li2-CO3, borated paraffin. 0.5 mm Cd sheet for 2286500500025 energy range above 0.7 eV. Energy calibration of 2286500500026 neutron beam was made by 4.92eV Au, 132.eV Co, 2286500500027 336.eV and 2.37keV Mn resonances 2286500500028 SAMPLE .NaI-129 powder : 60.% purity, 2286500500029 isotopic comp. I-129 (68.%); I-127 (32.%) 2286500500030 0.087 g/cm2, 1.9 mm thickness, 2286500500031 2.0 cm in diam. 2286500500032 .NaI-127 powder : 60.% purity, 2286500500033 isotopic comp. I-127 (100.%) 2286500500034 0.129 g/cm2, 1.9 mm thickness, 2286500500035 2.0 cm in diam. 2286500500036 boron powder of b-10 - 96.98% and b-11 - 3.02% 2286500500037 (packed in aluminium case of 0.1 mm thickness) : 2286500500038 99.999% purity, 2286500500039 0.872g/cm2, 52.42atom/kb, 8.0mm thickness, 2286500500040 1.8*1.8 cm2 dimensions. 2286500500041 graphite plate : 99.99% purity, 2286500500042 1.892g/cm2, 94.96atom/kb, 10.0mm thickness, 2286500500043 1.8*1.8 cm2 dimensions. 2286500500044 The NaI-127 sample is made of the same material and 2286500500045 size as the NaI-129, except for 127I instead of 129I. 2286500500046 ERR-ANALYS (ERR-T,4.4,180.) Total uncertainty 2286500500047 (ERR-S,0.5,180.) Statistical error. Poor statistics are2286500500048 observed in general in the cross section minimum 2286500500049 region, due to the low SIB ratio. 2286500500050 (ERR-1) Deviation from 1/v-form in B-10(n,alpha) c-s 2286500500051 (ERR-2) Data normalization to the reference value 2286500500052 at 0.0253 eV 2286500500053 (ERR-3) Correction error for neutron self-shielding 2286500500054 and/or scattering effects 2286500500055 COMMENT No any response from the author. 2286500500056 STATUS (UNOBT)Data presented on fig. 2 of 2002BRUSS,,588,2002 2286500500057 HISTORY (20191103C) SD 2286500500058 ENDBIB 56 0 2286500500059 COMMON 3 3 2286500500060 ERR-1 ERR-2 ERR-3 2286500500061 PER-CENT PER-CENT PER-CENT 2286500500062 2.4 2.0 3.0 2286500500063 ENDCOMMON 3 0 2286500500064 NODATA 0 0 2286500500065 ENDSUBENT 64 0 2286500599999 ENDENTRY 5 0 2286599999999