ENTRY 14369 20130625 13931436900000001 SUBENT 14369001 20130625 13931436900100001 BIB 11 42 1436900100002 TITLE Nuclear Fission 1436900100003 AUTHOR (J.S.Fraser,J.C.D.Milton) 1436900100004 REFERENCE (J,ARN,16,379,1966) 1436900100005 #doi:10.1146/annurev.ns.16.120166.002115 1436900100006 (C,65SALZBURG,2,39,1965) 1436900100007 INSTITUTE (1CANCRC) 1436900100008 FACILITY (REAC,1CANCRC) NRU reactor. 1436900100009 PART-DET (FF,N,G) 1436900100010 DETECTOR (SCIN) The neutrons were detected in cylinders of NE 1436900100011 102 plastic 5-in. diam. x 2-in.. thick after 1436900100012 traversing a 106-cm flight path. 1436900100013 METHOD (TOF,FNB) Fragment flight paths were 125 and 99 cm. 1436900100014 The neutron beam was filtered through 6 in of bismuth 1436900100015 and 8 in of quartz to give a thermal neutron flux of 1436900100016 2 x 108 n/cm2 s. The efficiency of the neutron 1436900100017 detectors was obtained by comparing the observed 1436900100018 time-of-flight spectrum in each of the counter with 1436900100019 the accurately known 235U neutron spectrum. 1436900100020 ANALYSIS After a preliminary inspection, the neutron 1436900100021 time-of-flight spectrum is divided into four regions: 1436900100022 background, gamma, neutron and background. In the 1436900100023 first pass fission fragments associated with the two 1436900100024 background regions are sorted to determine the 1436900100025 "normal" distribution, i.e. number of fissions as a 1436900100026 function of mass and energy without reference to 1436900100027 neutron emission. On the second pass, gamma events 1436900100028 are sorted and a Gaussian fitted to the peak to 1436900100029 obtain the zero of the neutron time scale. On the 1436900100030 third pass, events in the two background regions are 1436900100031 folded into the neutron region in such a way that 1436900100032 there is a one-to-one correspondence between a 1436900100033 channel in the neutron region and one in the 1436900100034 background region. The treatment of the neutron 1436900100035 region in the fourth pass is identical to described 1436900100036 above, except for the sign of the weights and the 1436900100037 conversion of the channel numbers. In addition to the 1436900100038 momentum information for all fragment masses and 1436900100039 energies, the computer also stores the complete 1436900100040 velocity spectrum for the two major fragment groups, 1436900100041 light and heavy. 1436900100042 ERR-ANALYS (DATA-ERR) No details are given. 1436900100043 HISTORY (20130625C) BP 1436900100044 ENDBIB 42 0 1436900100045 COMMON 1 3 1436900100046 EN 1436900100047 EV 1436900100048 0.0253 1436900100049 ENDCOMMON 3 0 1436900100050 ENDSUBENT 49 0 1436900199999 SUBENT 14369002 20130625 13931436900200001 BIB 2 3 1436900200002 REACTION (94-PU-239(N,F)MASS,PR/FRG,NU) Multiplicity of 1436900200003 neutrons emitted from the fragment specified. 1436900200004 STATUS (CURVE) Fig.34, page 434, Reference 1. 1436900200005 ENDBIB 3 0 1436900200006 NOCOMMON 0 0 1436900200007 DATA 3 80 1436900200008 MASS DATA DATA-ERR 1436900200009 NO-DIM NO-DIM NO-DIM 1436900200010 8.000E+01 2.339E-02 2.780E-01 1436900200011 8.100E+01 2.219E-01 2.701E-01 1436900200012 8.200E+01 7.303E-01 1.946E-01 1436900200013 8.300E+01 6.310E-01 1.629E-01 1436900200014 8.400E+01 6.230E-01 1.152E-01 1436900200015 8.500E+01 9.367E-01 1.072E-01 1436900200016 8.600E+01 8.096E-01 9.137E-02 1436900200017 8.700E+01 1.139E+00 8.737E-02 1436900200018 8.800E+01 1.103E+00 6.752E-02 1436900200019 8.900E+01 1.191E+00 6.753E-02 1436900200020 9.000E+01 1.218E+00 7.547E-02 1436900200021 9.100E+01 1.310E+00 5.959E-02 1436900200022 9.200E+01 1.457E+00 5.164E-02 1436900200023 9.300E+01 1.397E+00 5.163E-02 1436900200024 9.400E+01 1.453E+00 5.958E-02 1436900200025 9.500E+01 1.568E+00 4.767E-02 1436900200026 9.600E+01 1.600E+00 3.575E-02 1436900200027 9.700E+01 1.607E+00 3.575E-02 1436900200028 9.800E+01 1.560E+00 3.972E-02 1436900200029 9.900E+01 1.536E+00 3.575E-02 1436900200030 1.000E+02 1.472E+00 2.781E-02 1436900200031 1.010E+02 1.504E+00 4.767E-02 1436900200032 1.020E+02 1.508E+00 2.781E-02 1436900200033 1.030E+02 1.575E+00 3.178E-02 1436900200034 1.040E+02 1.583E+00 2.383E-02 1436900200035 1.050E+02 1.583E+00 3.177E-02 1436900200036 1.060E+02 1.595E+00 3.178E-02 1436900200037 1.070E+02 1.615E+00 4.370E-02 1436900200038 1.080E+02 1.750E+00 4.766E-02 1436900200039 1.090E+02 1.968E+00 5.560E-02 1436900200040 1.100E+02 1.988E+00 5.163E-02 1436900200041 1.110E+02 2.135E+00 1.033E-01 1436900200042 1.120E+02 2.310E+00 9.930E-02 1436900200043 1.130E+02 2.159E+00 1.152E-01 1436900200044 1.140E+02 2.214E+00 1.589E-01 1436900200045 1.150E+02 2.202E+00 1.986E-01 1436900200046 1.160E+02 2.250E+00 2.463E-01 1436900200047 1.170E+02 2.107E+00 2.701E-01 1436900200048 1.180E+02 2.167E+00 2.860E-01 1436900200049 1.190E+02 1.877E+00 2.860E-01 1436900200050 1.200E+02 1.054E+00 3.535E-01 1436900200051 1.210E+02 9.550E-01 2.939E-01 1436900200052 1.220E+02 1.281E+00 2.820E-01 1436900200053 1.230E+02 5.299E-01 2.383E-01 1436900200054 1.240E+02 4.782E-01 2.343E-01 1436900200055 1.250E+02 5.814E-01 2.344E-01 1436900200056 1.260E+02 9.285E-02 1.192E-01 1436900200057 1.270E+02 2.437E-01 9.930E-02 1436900200058 1.280E+02 3.231E-01 6.752E-02 1436900200059 1.290E+02 2.834E-01 5.562E-02 1436900200060 1.300E+02 4.104E-01 6.752E-02 1436900200061 1.310E+02 4.978E-01 4.766E-02 1436900200062 1.320E+02 5.652E-01 2.781E-02 1436900200063 1.330E+02 7.122E-01 3.178E-02 1436900200064 1.340E+02 8.710E-01 3.574E-02 1436900200065 1.350E+02 1.054E+00 2.382E-02 1436900200066 1.360E+02 1.216E+00 3.176E-02 1436900200067 1.370E+02 1.355E+00 2.781E-02 1436900200068 1.380E+02 1.451E+00 3.178E-02 1436900200069 1.390E+02 1.455E+00 3.178E-02 1436900200070 1.400E+02 1.482E+00 3.972E-02 1436900200071 1.410E+02 1.486E+00 2.781E-02 1436900200072 1.420E+02 1.439E+00 2.781E-02 1436900200073 1.430E+02 1.490E+00 3.575E-02 1436900200074 1.440E+02 1.633E+00 3.972E-02 1436900200075 1.450E+02 1.653E+00 5.163E-02 1436900200076 1.460E+02 1.732E+00 6.752E-02 1436900200077 1.470E+02 1.764E+00 7.151E-02 1436900200078 1.480E+02 1.907E+00 8.739E-02 1436900200079 1.490E+02 1.851E+00 7.944E-02 1436900200080 1.500E+02 2.149E+00 9.533E-02 1436900200081 1.510E+02 2.018E+00 9.135E-02 1436900200082 1.520E+02 2.320E+00 1.231E-01 1436900200083 1.530E+02 2.352E+00 1.430E-01 1436900200084 1.540E+02 2.272E+00 1.470E-01 1436900200085 1.550E+02 2.352E+00 1.708E-01 1436900200086 1.560E+02 2.272E+00 1.430E-01 1436900200087 1.570E+02 3.344E+00 3.019E-01 1436900200088 1.580E+02 2.629E+00 3.257E-01 1436900200089 1.590E+02 2.232E+00 3.535E-01 1436900200090 ENDDATA 82 0 1436900200091 ENDSUBENT 90 0 1436900299999 SUBENT 14369003 20130625 13931436900300001 BIB 2 3 1436900300002 REACTION (92-U-235(N,F)MASS,PR/FRG,NU) Multiplicity of 1436900300003 neutrons emitted from the fragment specified 1436900300004 STATUS (CURVE) Fig.4, page 46, Reference 2. 1436900300005 ENDBIB 3 0 1436900300006 NOCOMMON 0 0 1436900300007 DATA 3 77 1436900300008 MASS DATA DATA-ERR 1436900300009 NO-DIM NO-DIM NO-DIM 1436900300010 8.000E+01 8.943E-01 2.740E-01 1436900300011 8.100E+01 7.448E-01 1.957E-01 1436900300012 8.200E+01 6.801E-01 1.761E-01 1436900300013 8.300E+01 8.569E-01 1.241E-01 1436900300014 8.400E+01 9.423E-01 9.140E-02 1436900300015 8.500E+01 1.021E+00 8.469E-02 1436900300016 8.600E+01 1.022E+00 7.164E-02 1436900300017 8.700E+01 1.185E+00 7.164E-02 1436900300018 8.800E+01 1.251E+00 5.207E-02 1436900300019 8.900E+01 1.395E+00 5.216E-02 1436900300020 9.000E+01 1.618E+00 3.263E-02 1436900300021 9.100E+01 1.592E+00 5.211E-02 1436900300022 9.200E+01 1.567E+00 2.601E-02 1436900300023 9.300E+01 1.620E+00 3.254E-02 1436900300024 9.400E+01 1.672E+00 3.258E-02 1436900300025 9.500E+01 1.777E+00 2.606E-02 1436900300026 9.600E+01 1.876E+00 3.276E-02 1436900300027 9.700E+01 1.694E+00 3.271E-02 1436900300028 9.800E+01 1.570E+00 3.258E-02 1436900300029 9.900E+01 1.623E+00 3.263E-02 1436900300030 1.000E+02 1.721E+00 3.258E-02 1436900300031 1.010E+02 1.774E+00 3.906E-02 1436900300032 1.020E+02 1.723E+00 3.254E-02 1436900300033 1.030E+02 1.677E+00 3.249E-02 1436900300034 1.040E+02 1.776E+00 3.258E-02 1436900300035 1.050E+02 1.809E+00 5.864E-02 1436900300036 1.060E+02 1.966E+00 7.173E-02 1436900300037 1.070E+02 2.319E+00 8.474E-02 1436900300038 1.080E+02 2.855E+00 1.108E-01 1436900300039 1.090E+02 2.457E+00 1.566E-01 1436900300040 1.100E+02 1.858E+00 2.152E-01 1436900300041 1.110E+02 1.454E+00 2.480E-01 1436900300042 1.120E+02 2.850E+00 2.741E-01 1436900300043 1.130E+02 2.107E+00 3.589E-01 1436900300044 1.160E+02 3.159E+00 3.589E-01 1436900300045 1.170E+02 1.907E+00 4.568E-01 1436900300046 1.180E+02 1.705E+00 3.785E-01 1436900300047 1.190E+02 1.119E+00 4.828E-01 1436900300048 1.200E+02 9.954E-01 3.784E-01 1436900300049 1.210E+02 8.132E-01 5.741E-01 1436900300050 1.220E+02 1.101E+00 4.568E-01 1436900300051 1.230E+02 4.881E-01 6.916E-01 1436900300052 1.240E+02 2.159E+00 6.787E-01 1436900300053 1.250E+02 9.069E-01 7.111E-01 1436900300054 1.260E+02 7.508E-01 4.370E-01 1436900300055 1.270E+02 7.514E-01 2.741E-01 1436900300056 1.280E+02 1.908E-01 8.482E-01 1436900300057 1.290E+02 2.958E-01 3.457E-01 1436900300058 1.300E+02 2.507E-01 2.937E-01 1436900300059 1.310E+02 4.666E-01 1.239E-01 1436900300060 1.320E+02 4.280E-01 1.305E-01 1436900300061 1.330E+02 6.569E-01 9.126E-02 1436900300062 1.340E+02 7.488E-01 5.864E-02 1436900300063 1.350E+02 9.973E-01 6.521E-02 1436900300064 1.360E+02 1.181E+00 3.919E-02 1436900300065 1.370E+02 1.129E+00 3.254E-02 1436900300066 1.380E+02 1.325E+00 3.254E-02 1436900300067 1.390E+02 1.254E+00 5.868E-02 1436900300068 1.400E+02 1.255E+00 5.224E-02 1436900300069 1.410E+02 1.281E+00 2.601E-02 1436900300070 1.420E+02 1.354E+00 5.868E-02 1436900300071 1.430E+02 1.328E+00 3.906E-02 1436900300072 1.440E+02 1.303E+00 7.164E-02 1436900300073 1.450E+02 1.316E+00 3.249E-02 1436900300074 1.460E+02 1.402E+00 5.211E-02 1436900300075 1.470E+02 1.402E+00 5.211E-02 1436900300076 1.480E+02 1.722E+00 3.258E-02 1436900300077 1.490E+02 1.664E+00 5.207E-02 1436900300078 1.500E+02 1.972E+00 6.512E-02 1436900300079 1.510E+02 1.770E+00 8.469E-02 1436900300080 1.520E+02 2.018E+00 7.826E-02 1436900300081 1.530E+02 1.608E+00 1.043E-01 1436900300082 1.540E+02 2.346E+00 1.239E-01 1436900300083 1.550E+02 1.713E+00 1.631E-01 1436900300084 1.560E+02 2.060E+00 2.087E-01 1436900300085 1.570E+02 2.504E+00 1.891E-01 1436900300086 1.580E+02 1.559E+00 3.980E-01 1436900300087 ENDDATA 79 0 1436900300088 ENDSUBENT 87 0 1436900399999 SUBENT 14369004 20130625 13931436900400001 BIB 2 3 1436900400002 REACTION (92-U-233(N,F)MASS,PR/FRG,NU) Multiplicity of 1436900400003 neutrons emitted from the fragment specified. 1436900400004 STATUS (CURVE) Fig.5, page 47, Reference 2. 1436900400005 ENDBIB 3 0 1436900400006 NOCOMMON 0 0 1436900400007 DATA 3 33 1436900400008 MASS DATA DATA-ERR 1436900400009 NO-DIM NO-DIM NO-DIM 1436900400010 8.000E+01 5.187E-01 2.053E-01 1436900400011 8.200E+01 4.450E-01 1.560E-01 1436900400012 8.400E+01 6.505E-01 7.394E-02 1436900400013 8.600E+01 8.726E-01 1436900400014 8.800E+01 7.989E-01 1436900400015 9.000E+01 1.169E+00 1436900400016 9.200E+01 1.555E+00 1436900400017 9.400E+01 1.514E+00 1436900400018 9.600E+01 1.539E+00 1436900400019 9.800E+01 1.630E+00 1436900400020 1.000E+02 1.564E+00 1436900400021 1.020E+02 1.762E+00 1436900400022 1.040E+02 2.090E+00 1.314E-01 1436900400023 1.060E+02 2.780E+00 1.725E-01 1436900400024 1.080E+02 3.618E+00 3.285E-01 1436900400025 1.100E+02 3.380E+00 5.585E-01 1436900400026 1.260E+02 8.883E-02 2.792E-01 1436900400027 1.280E+02 6.147E-01 1.560E-01 1436900400028 1.300E+02 1.632E-01 1.068E-01 1436900400029 1.320E+02 2.703E-01 1436900400030 1.340E+02 4.430E-01 1436900400031 1.360E+02 6.157E-01 1436900400032 1.380E+02 8.048E-01 1436900400033 1.400E+02 1.134E+00 1436900400034 1.420E+02 1.027E+00 1436900400035 1.440E+02 1.126E+00 1436900400036 1.460E+02 1.340E+00 1436900400037 1.480E+02 1.553E+00 1.068E-01 1436900400038 1.500E+02 1.973E+00 1.561E-01 1436900400039 1.520E+02 2.227E+00 1.971E-01 1436900400040 1.540E+02 1.809E+00 2.956E-01 1436900400041 1.560E+02 2.483E+00 3.449E-01 1436900400042 1.580E+02 2.926E+00 6.078E-01 1436900400043 ENDDATA 35 0 1436900400044 ENDSUBENT 43 0 1436900499999 SUBENT 14369005 20130625 13931436900500001 BIB 2 3 1436900500002 REACTION (92-U-233(N,F)MASS,PR,KE,N) Energy of neutrons 1436900500003 emitted with the fragment specified. 1436900500004 STATUS (CURVE) Fig.5, page 47, Reference 2. 1436900500005 ENDBIB 3 0 1436900500006 NOCOMMON 0 0 1436900500007 DATA 3 32 1436900500008 MASS DATA DATA-ERR 1436900500009 NO-DIM MEV MEV 1436900500010 8.000E+01 1.790E+00 6.958E-01 1436900500011 8.200E+01 9.932E-01 5.042E-01 1436900500012 8.400E+01 1.155E+00 1.714E-01 1436900500013 8.600E+01 1.120E+00 7.057E-02 1436900500014 8.800E+01 7.466E-01 4.035E-02 1436900500015 9.000E+01 1.075E+00 1436900500016 9.200E+01 1.231E+00 1436900500017 9.400E+01 1.110E+00 1436900500018 9.600E+01 1.161E+00 1436900500019 9.800E+01 1.176E+00 1436900500020 1.000E+02 1.206E+00 2.017E-02 1436900500021 1.020E+02 1.222E+00 4.536E-02 1436900500022 1.040E+02 1.388E+00 8.572E-02 1436900500023 1.060E+02 1.499E+00 9.076E-02 1436900500024 1.080E+02 1.676E+00 1.462E-01 1436900500025 1.100E+02 2.009E+00 2.067E-01 1436900500026 1.280E+02 1.839E+00 3.429E-01 1436900500027 1.300E+02 8.304E-01 3.479E-01 1436900500028 1.320E+02 1.410E+00 4.487E-01 1436900500029 1.340E+02 1.758E+00 2.067E-01 1436900500030 1.360E+02 1.275E+00 1.361E-01 1436900500031 1.380E+02 1.285E+00 1.059E-01 1436900500032 1.400E+02 1.250E+00 6.552E-02 1436900500033 1.420E+02 1.083E+00 8.571E-02 1436900500034 1.440E+02 1.083E+00 6.051E-02 1436900500035 1.460E+02 1.169E+00 8.572E-02 1436900500036 1.480E+02 8.014E-01 5.547E-02 1436900500037 1.500E+02 1.346E+00 1.008E-01 1436900500038 1.520E+02 1.588E+00 1.311E-01 1436900500039 1.540E+02 6.203E-01 1.765E-01 1436900500040 1.560E+02 2.340E+00 3.076E-01 1436900500041 1.580E+02 1.513E+00 2.572E-01 1436900500042 ENDDATA 34 0 1436900500043 ENDSUBENT 42 0 1436900599999 ENDENTRY 5 0 1436999999999