ENTRY 14201 20111003 13761420100000001 SUBENT 14201001 20111003 13761420100100001 BIB 12 41 1420100100002 TITLE Spectrum of photons emitted in coincidence with 1420100100003 fission of 235U by thermal neutrons 1420100100004 AUTHOR (R.W.Peelle,F.C.Maienschein) 1420100100005 INSTITUTE (1USAORL) 1420100100006 REFERENCE (J,PR/C,3,373,1971) 1420100100007 FACILITY (REAC,1USAORL) Experiment performed at the thermal 1420100100008 column of the Oak Ridge graphite reactor. 1420100100009 SAMPLE Enriched uranium samples with weight of 0.019,0.023 1420100100010 and 0.23 g were used for gamma ray spectra 1420100100011 measurement with single crystal, compton spectrometer 1420100100012 and pair spectrometer, respectively 1420100100013 DETECTOR (NAICR) In the energy range 0.01 - 0.8 MeV a single 1420100100014 crystal NaI(Tl) spectrometer with crystal diameter of 1420100100015 4.45cm and height of 2.54 cm was used. 1420100100016 In the energy range 0.4-2.4 MeV a Compton spectrometer 1420100100017 with dimensions of 0.95 cm x 2.2cm x 2.2 cm and side 1420100100018 crystal dimensions of 3.8cm x 3.8cm x 2.54 cm was used.1420100100019 (BPAIR) In energy range 1.6-10.5 MeV a pair 1420100100020 spectrometer with central crystal dimensions of 1420100100021 1.9cm x 2.5cm x 2.5 cm was used. 1420100100022 Annihilation quanta were detected in NaI(Tl) crystals 1420100100023 with diameter of 5.1 cm. 1420100100024 (FISCH)Spiral-wound fission chamber was used at 1420100100025 higher energies and the parallel plate chamber at 1420100100026 lower gamma ray energies 1420100100027 METHOD (TOF,COINC) Coincidence was required between fission 1420100100028 chamber and gamma spectrometer and time of flight was 1420100100029 used to discriminate neutron induced events in gamma 1420100100030 ray spectrometer. 1420100100031 ANALYSIS Photon energy spectrum was obtained from measured 1420100100032 pulse height spectrum by unfolding procedure with 1420100100033 empirically chosen response functions. 1420100100034 CORRECTION Data corrected for 1420100100035 - background caused by neutrons 1420100100036 - background from random coincidences 1420100100037 - counting losses 1420100100038 ERR-ANALYS (ERR-T) Total uncertainty 1420100100039 (ERR-SYS,2.8,50.0) Total systematic uncertainty 1420100100040 (ERR-1,1.9,50.0) Systematic uncertainty due to peak 1420100100041 efficiencies 1420100100042 HISTORY (20111003C) Compiled by S.H. 1420100100043 ENDBIB 41 0 1420100100044 COMMON 1 3 1420100100045 EN-DUMMY 1420100100046 EV 1420100100047 0.025 1420100100048 ENDCOMMON 3 0 1420100100049 ENDSUBENT 48 0 1420100199999 SUBENT 14201002 20111003 13761420100200001 BIB 3 4 1420100200002 REACTION (92-U-235(N,F)0-G-0,PR,FY/DE,,MXW) Energy spectrum of 1420100200003 prompt gamma rays from fission 1420100200004 PART-DET (G) Prompt gamma rays from fission 1420100200005 STATUS (CURVE) Data taken from fig. 5 of the reference 1420100200006 ENDBIB 4 0 1420100200007 NOCOMMON 0 0 1420100200008 DATA 4 198 1420100200009 E DATA DATA-MIN DATA-MAX 1420100200010 MEV PD/FIS/MEV PD/FIS/MEV PD/FIS/MEV 1420100200011 0.09 3.50E+00 1420100200012 0.10 4.25E+00 1420100200013 0.11 6.59E+00 1420100200014 0.11 5.38E+00 1420100200015 0.13 6.88E+00 1420100200016 0.14 7.49E+00 1420100200017 0.16 6.69E+00 1420100200018 0.18 5.43E+00 1420100200019 0.21 8.02E+00 1420100200020 0.22 6.61E+00 1420100200021 0.23 5.96E+00 1420100200022 0.24 4.74E+00 1420100200023 0.26 4.27E+00 1420100200024 0.28 4.81E+00 1420100200025 0.30 5.63E+00 1420100200026 0.33 6.33E+00 1420100200027 0.34 6.83E+00 7.59E+00 1420100200028 0.38 7.06E+00 7.47E+00 1420100200029 0.45 7.03E+00 7.44E+00 1420100200030 0.48 7.41E+00 7.90E+00 1420100200031 0.51 6.44E+00 7.06E+00 1420100200032 0.56 6.24E+00 6.76E+00 1420100200033 0.57 7.50E+00 7.88E+00 1420100200034 0.59 7.78E+00 8.13E+00 1420100200035 0.63 6.21E+00 7.21E+00 1420100200036 0.67 5.62E+00 6.21E+00 1420100200037 0.71 5.46E+00 6.19E+00 1420100200038 0.74 5.16E+00 5.95E+00 1420100200039 0.79 4.77E+00 5.08E+00 1420100200040 0.84 4.21E+00 4.69E+00 1420100200041 0.88 3.71E+00 4.11E+00 1420100200042 0.93 3.39E+00 3.74E+00 1420100200043 0.97 3.14E+00 3.43E+00 1420100200044 1.01 2.93E+00 3.24E+00 1420100200045 1.06 2.77E+00 3.06E+00 1420100200046 1.10 2.64E+00 2.93E+00 1420100200047 1.14 2.47E+00 2.79E+00 1420100200048 1.18 2.46E+00 2.77E+00 1420100200049 1.23 2.49E+00 2.74E+00 1420100200050 1.27 2.39E+00 2.66E+00 1420100200051 1.31 2.14E+00 2.37E+00 1420100200052 1.36 1.92E+00 2.10E+00 1420100200053 1.40 1.60E+00 1.82E+00 1420100200054 1.45 1.48E+00 1.61E+00 1420100200055 1.49 1.34E+00 1.47E+00 1420100200056 1.53 1.26E+00 1.38E+00 1420100200057 1.57 1.16E+00 1.28E+00 1420100200058 1.62 1.09E+00 1.22E+00 1420100200059 1.66 1.02E+00 1.17E+00 1420100200060 1.70 9.97E-01 1.11E+00 1420100200061 1.75 1.00E+00 1.10E+00 1420100200062 1.79 1.02E+00 1.11E+00 1420100200063 1.83 9.96E-01 1.11E+00 1420100200064 1.88 9.42E-01 1.02E+00 1420100200065 1.92 8.41E-01 9.43E-01 1420100200066 1.96 8.39E-01 9.33E-01 1420100200067 2.00 7.76E-01 8.81E-01 1420100200068 2.05 7.26E-01 8.05E-01 1420100200069 2.09 6.66E-01 7.51E-01 1420100200070 2.13 6.39E-01 7.15E-01 1420100200071 2.17 6.18E-01 6.93E-01 1420100200072 2.22 6.17E-01 6.75E-01 1420100200073 2.26 5.96E-01 6.46E-01 1420100200074 2.30 5.62E-01 6.17E-01 1420100200075 2.35 5.32E-01 5.90E-01 1420100200076 2.39 5.07E-01 5.56E-01 1420100200077 2.44 4.93E-01 5.32E-01 1420100200078 2.48 4.84E-01 5.28E-01 1420100200079 2.52 4.71E-01 5.11E-01 1420100200080 2.56 4.53E-01 5.00E-01 1420100200081 2.61 4.38E-01 4.89E-01 1420100200082 2.65 4.16E-01 4.69E-01 1420100200083 2.70 3.96E-01 4.47E-01 1420100200084 2.74 3.80E-01 4.23E-01 1420100200085 2.78 3.62E-01 4.01E-01 1420100200086 2.82 3.39E-01 3.74E-01 1420100200087 2.87 3.08E-01 3.38E-01 1420100200088 2.91 2.71E-01 3.10E-01 1420100200089 2.96 2.51E-01 2.85E-01 1420100200090 3.00 2.34E-01 2.70E-01 1420100200091 3.04 2.23E-01 2.68E-01 1420100200092 3.08 2.10E-01 2.57E-01 1420100200093 3.13 1.99E-01 2.44E-01 1420100200094 3.17 1.87E-01 2.30E-01 1420100200095 3.21 1.85E-01 2.19E-01 1420100200096 3.26 1.84E-01 2.09E-01 1420100200097 3.30 1.82E-01 2.06E-01 1420100200098 3.34 1.79E-01 2.01E-01 1420100200099 3.39 1.77E-01 2.00E-01 1420100200100 3.43 1.61E-01 1.84E-01 1420100200101 3.47 1.45E-01 1.64E-01 1420100200102 3.52 1.31E-01 1.51E-01 1420100200103 3.56 1.25E-01 1.45E-01 1420100200104 3.60 1.24E-01 1.42E-01 1420100200105 3.65 1.22E-01 1.41E-01 1420100200106 3.69 1.19E-01 1.41E-01 1420100200107 3.73 1.13E-01 1.43E-01 1420100200108 3.78 1.06E-01 1.45E-01 1420100200109 3.82 9.87E-02 1.39E-01 1420100200110 3.86 9.21E-02 1.32E-01 1420100200111 3.91 8.60E-02 1.25E-01 1420100200112 3.95 8.05E-02 1.20E-01 1420100200113 3.99 7.33E-02 1.16E-01 1420100200114 4.04 6.93E-02 1.15E-01 1420100200115 4.08 6.34E-02 1.10E-01 1420100200116 4.12 5.75E-02 1.01E-01 1420100200117 4.16 5.26E-02 9.47E-02 1420100200118 4.21 4.89E-02 8.83E-02 1420100200119 4.25 4.38E-02 8.52E-02 1420100200120 4.29 4.01E-02 8.22E-02 1420100200121 4.32 6.83E-02 8.20E-02 1420100200122 4.36 6.56E-02 7.91E-02 1420100200123 4.40 5.88E-02 7.29E-02 1420100200124 4.45 5.41E-02 6.70E-02 1420100200125 4.49 4.93E-02 6.22E-02 1420100200126 4.53 4.70E-02 5.87E-02 1420100200127 4.57 4.56E-02 5.69E-02 1420100200128 4.62 4.43E-02 5.56E-02 1420100200129 4.66 4.31E-02 5.33E-02 1420100200130 4.70 3.78E-02 4.85E-02 1420100200131 4.75 3.27E-02 4.35E-02 1420100200132 4.79 2.91E-02 3.91E-02 1420100200133 4.83 2.60E-02 3.55E-02 1420100200134 4.87 2.34E-02 3.31E-02 1420100200135 4.91 2.17E-02 3.08E-02 1420100200136 4.96 1.95E-02 2.88E-02 1420100200137 5.00 1.87E-02 2.80E-02 1420100200138 5.04 1.81E-02 2.76E-02 1420100200139 5.08 1.75E-02 2.74E-02 1420100200140 5.13 1.74E-02 2.74E-02 1420100200141 5.17 1.82E-02 2.83E-02 1420100200142 5.21 1.97E-02 2.97E-02 1420100200143 5.26 2.07E-02 3.11E-02 1420100200144 5.30 2.14E-02 3.13E-02 1420100200145 5.34 2.00E-02 2.97E-02 1420100200146 5.39 1.97E-02 2.84E-02 1420100200147 5.43 1.85E-02 2.70E-02 1420100200148 5.47 1.80E-02 2.60E-02 1420100200149 5.51 1.70E-02 2.45E-02 1420100200150 5.56 1.61E-02 2.38E-02 1420100200151 5.60 1.54E-02 2.29E-02 1420100200152 5.64 1.43E-02 2.17E-02 1420100200153 5.68 1.34E-02 2.07E-02 1420100200154 5.73 1.26E-02 1.97E-02 1420100200155 5.77 1.19E-02 1.88E-02 1420100200156 5.81 1.11E-02 1.81E-02 1420100200157 5.86 1.05E-02 1.75E-02 1420100200158 5.90 1.01E-02 1.69E-02 1420100200159 5.94 9.92E-03 1.64E-02 1420100200160 5.98 9.51E-03 1.60E-02 1420100200161 6.02 9.23E-03 1.55E-02 1420100200162 6.07 8.80E-03 1.51E-02 1420100200163 6.11 8.53E-03 1.48E-02 1420100200164 6.15 8.28E-03 1.43E-02 1420100200165 6.20 8.01E-03 1.39E-02 1420100200166 6.24 7.62E-03 1.35E-02 1420100200167 6.28 7.16E-03 1.30E-02 1420100200168 6.33 6.68E-03 1.23E-02 1420100200169 6.37 6.25E-03 1.18E-02 1420100200170 6.41 5.88E-03 1.12E-02 1420100200171 6.45 5.53E-03 1.09E-02 1420100200172 6.50 5.15E-03 1.04E-02 1420100200173 6.54 4.88E-03 9.92E-03 1420100200174 6.58 4.55E-03 9.47E-03 1420100200175 6.62 4.47E-03 9.36E-03 1420100200176 6.67 4.40E-03 9.26E-03 1420100200177 6.71 4.34E-03 9.09E-03 1420100200178 6.75 4.27E-03 8.99E-03 1420100200179 6.80 4.18E-03 8.90E-03 1420100200180 6.84 4.15E-03 8.77E-03 1420100200181 6.88 4.07E-03 8.68E-03 1420100200182 6.92 4.01E-03 8.50E-03 1420100200183 6.97 2.79E-03 8.20E-03 1420100200184 6.97 3.88E-03 8.24E-03 1420100200185 7.01 2.72E-03 7.42E-03 1420100200186 7.06 6.28E-03 1420100200187 7.10 5.59E-03 1420100200188 7.14 4.86E-03 1420100200189 7.18 4.20E-03 1420100200190 7.23 3.66E-03 1420100200191 7.27 3.20E-03 1420100200192 7.31 2.80E-03 1420100200193 7.35 2.49E-03 1420100200194 7.40 2.18E-03 1420100200195 7.44 1.87E-03 1420100200196 7.48 1.67E-03 1420100200197 7.52 1.47E-03 1420100200198 7.57 1.29E-03 1420100200199 7.61 1.26E-03 1420100200200 7.66 1.24E-03 1420100200201 7.70 1.22E-03 1420100200202 7.74 1.21E-03 1420100200203 7.78 1.19E-03 1420100200204 7.83 1.17E-03 1420100200205 7.87 1.16E-03 1420100200206 7.91 1.13E-03 1420100200207 7.95 1.12E-03 1420100200208 8.01 1.10E-03 1420100200209 ENDDATA 200 0 1420100200210 ENDSUBENT 209 0 1420100299999 SUBENT 14201003 20111003 13761420100300001 BIB 3 3 1420100300002 REACTION (92-U-235(N,F)0-G-0,PR/PAR,FY,,MXW) 1420100300003 PART-DET (G) Prompt gamma rays from fission 1420100300004 STATUS (TABLE) Data taken from tab. 2 of the reference 1420100300005 ENDBIB 3 0 1420100300006 NOCOMMON 0 0 1420100300007 DATA 4 2 1420100300008 E-MIN E-MAX DATA DATA-ERR 1420100300009 MEV MEV PRD/FIS PRD/FIS 1420100300010 0.01 10.5 8.13 0.35 1420100300011 0.14 10.0 7.45 0.32 1420100300012 ENDDATA 4 0 1420100300013 ENDSUBENT 12 0 1420100399999 ENDENTRY 3 0 1420199999999