ENTRY 30639 20090830 31403063900000001 SUBENT 30639001 20090830 31403063900100001 BIB 12 37 3063900100002 INSTITUTE (3HUNKOS,3HUNII ) 3063900100003 REFERENCE (J,AK,18,317,1976) Final detailed results 3063900100004 (P,INDC(SEC)-61,53,197710) Brief,graph only 3063900100005 AUTHOR (S.Daroczy,P.Raics,S.Nagy,L.Koever,I.Hamvas,E.German) 3063900100006 TITLE Experimental results of mass distribution of U-238 3063900100007 fission induced by 14 MeV neutrons 3063900100008 FACILITY (CCW,3HUNKOS) 3063900100009 SAMPLE Natural uranium,U308.Details for individual samples of 3063900100010 the 3 experiments are given in subentries 2,3,4,7,8. 3063900100011 METHOD (GSPEC) Direct gamma-spectrometry of fission products 3063900100012 ANALYSIS (DECAY) 3063900100013 COMMENT The work consists of 3 different experiments. Results 3063900100014 are given for each experiment as well as weighted 3063900100015 averages and deduced chain and fractional yields. 3063900100016 Subent 02-experiment 1 (1969),cumulative yields 3063900100017 Subent 03-experiment 2 (1971),cumulative yields 3063900100018 Subent 04-experiment 3 (1973),cumulative yields 3063900100019 Subent 05-weighted average of cumulative yields 3063900100020 Subent 06-chain yields 3063900100021 Subent 07-experiment 1 (1969),independent yields 3063900100022 Subent 08-experiment 2 (1971),independent yields 3063900100023 Subent 09-weighted average of independent yields 3063900100024 Subent 10-fractional independent yields 3063900100025 STATUS (TABLE) Data compiled from Tables II and III 3063900100026 of first reference 3063900100027 HISTORY (19821105C) ML. 3063900100028 (19841212U) ML.Decay data moved to respect. subentries 3063900100029 Decay flags changed and data section 3063900100030 rearranged avoiding repetion of column 3063900100031 headings, subentries 2,3,4,7,8. 3063900100032 EN-ERR corrected in subentry 3. 3063900100033 (20090725A) SD:Updated to new date formats,lower case. 3063900100034 CORRECTION Gamma spectra were corrected for random pulse pile-up 3063900100035 and coincidences. 3063900100036 Corrections for gamma ray attenuation were determined 3063900100037 experimentally using uranium and thorium samples of 3063900100038 different thicknesses. 3063900100039 ENDBIB 37 0 3063900100040 NOCOMMON 0 0 3063900100041 ENDSUBENT 40 0 3063900199999 SUBENT 30639002 20090830 31403063900200001 BIB 13 91 3063900200002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) Long lived products 3063900200003 EXP-YEAR (1969) First experiment 3063900200004 INC-SOURCE Neutron flux=(7.80+-0.36)*10**6 n/s/*cm2 random 3063900200005 error,or +-3% systematic error 3063900200006 Irradiation time=29.25 hours 3063900200007 Number of fission events = 5.41*10**9 3063900200008 SAMPLE 2640 grams,thickness=1.47 mm or 921.4 mg/cm2, 3063900200009 diameter=19.1 mm. 3063900200010 DETECTOR (GELI).27 cm3, 4000 channel pulse height analyser, 3063900200011 resolution at 662 keV = 7.3 keV. 3063900200012 ANALYSIS 47 gamma spectra were recorded and analysed by the 3063900200013 computer program Sirius, based on a least squares 3063900200014 fitting procedure. Complete decay curves from 1.4 hrs. 3063900200015 to 149 days after irradiation were analysed. 3063900200016 DECAY-DATA Parent-daughter relationships indicated by flags 3063900200017 ((1.)38-SR-91,9.48HR,DG,653.0,0.111) 3063900200018 ((2.)38-SR-91,9.48HR,DG,749.8,0.231) 3063900200019 ((3.)38-SR-91,9.48HR,DG,1024.3,0.334) 3063900200020 ((4.)38-SR-91,9.48HR) 3063900200021 ((4.)39-Y-91-M,49.7MIN,DG,555.6,0.558) 3063900200022 ((5.)38-SR-92,2.71HR,DG,1383.9,0.9) 3063900200023 ((6.)40-ZR-95,62.5D) 3063900200024 ((6.)41-NB-95-G,35.1D,DG,765.8,0.998) 3063900200025 ((7.)40-ZR-97,16.8HR) 3063900200026 ((7.)41-NB-97-G,73.6MIN,DG,658.2,0.981) 3063900200027 ((8.)40-ZR-97,16.8HR) 3063900200028 ((8.)41-NB-97-M,54.SEC,DG,743.4,0.933) 3063900200029 ((9.)42-MO-99,66.02HR,DG,739.6,0.120) 3063900200030 ((10.)42-MO-99,66.02HR) 3063900200031 ((10.)43-TC-99-M,6.02HR,DG,140.4,0.810) 3063900200032 ((11.)44-RU-103,39.6D,DG,497.1,0.89) 3063900200033 ((12.)44-RU-105,4.44HR,DG,724.2,0.49) 3063900200034 ((13.)44-RU-105,4.44HR) 3063900200035 ((13.)45-RH-105-G,35.5HR,DG,319.2,0.192)includes 195mRh3063900200036 ((14.)46-PD-112,20.1HR) daughter 112Ag measured 3063900200037 ((14.)47-AG-112,3.13HR,DG,617.4,0.429) 3063900200038 ((15.)51-SB-127,3.80D,DG,684.9,0.357) 3063900200039 ((16.)53-I-131,8.041D,DG,364.5,0.820) 3063900200040 ((17.)52-TE-132,78.HR,DG,228.2,0.885) 3063900200041 ((18.)52-TE-132,78.HR) 3063900200042 ((18.)53-I-132-G,2.285HR,DG,522.6,0.156) 3063900200043 ((19.)52-TE-132,78.HR) 3063900200044 ((19.)53-I-132-G,2.285HR,DG,630.2,0.135) 3063900200045 ((20.)52-TE-132,78.HR) 3063900200046 ((20.)53-I-132-G,2.285HR,DG,667.7,0.980) 3063900200047 ((21.)52-TE-132,78.HR) 3063900200048 ((21.)53-I-132-G,2.285HR,DG,772.7,0.750) 3063900200049 ((22.)52-TE-132,78.HR) 3063900200050 ((22.)53-I-132-G,2.285HR,DG,954.6,0.167) 3063900200051 ((23.)53-I-133-G,20.8HR,DG,529.5,0.869) 3063900200052 ((24.)52-TE-134,42.MIN) 3063900200053 ((24.)53-I-134-G,52.6MIN,DG,847.0,0.954)includes 134mI 3063900200054 ((25.)53-I-135,6.585HR,DG,1260.5,0.286) 3063900200055 ((26.)53-I-135,6.585HR) 3063900200056 ((26.)54-XE-135-G,9.17HR,DG,249.7,0.903) incl. 135mXe 3063900200057 ((27.)56-BA-140,12.79D,DG,537.3,0.240) 3063900200058 ((28.)56-BA-140,12.79D) 3063900200059 ((28.)57-LA-140,40.23HR,DG,815.8,0.223) 3063900200060 ((29.)56-BA-140,12.79D) 3063900200061 ((29.)57-LA-140,40.23HR,DG,1596.2,0.953) 3063900200062 ((30.)56-BA-140,12.79D) 3063900200063 ((30.)57-LA-140,40.23HR,DG,487.0,0.46) 3063900200064 ((31.)58-CE-141,32.53D,DG,145.4,0.48) 3063900200065 ((32.)58-CE-143,33.0HR,DG,293.2,0.426) 3063900200066 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) Measured with Ge(Li) det. 3063900200067 MONIT-REF (,H.VONACH+,J,ZP,237,155,1970) 3063900200068 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.Sowerby+,AERE-R-7273,19733063900200069 COMMENT Preliminary results of this first experiment were 3063900200070 reported in earlier publications and compiled in 3063900200071 EXFOR30267. However, the values are either altered in 3063900200072 the final publication or withdrawn if they are 3063900200073 superseded by the second and/or third experiment with 3063900200074 much better detector resolution. 3063900200075 FLAG (1.) For the calculation of the yield of the fission 3063900200076 product given the half-life of its precursor is 3063900200077 also used. 3063900200078 (2.) The yield of the fission product given is derived 3063900200079 from a gamma-line of its daughter product often in3063900200080 equilibrium. 3063900200081 (3.) The weighted average of all yield data for Te-132 3063900200082 listed above this value. 3063900200083 ERR-ANALYS (DATA-ERR) All errors quoted are one standard 3063900200084 deviation. They include contributions from 3063900200085 * peak area and decay curve analysis, 3063900200086 * gamma-ray intensities, 3063900200087 * detector efficiency 3063900200088 * random error of the neutron flux. 3063900200089 Not included is 3063900200090 (ERR-1) the systematic 3% uncertainty in the neutron 3063900200091 flux determination,which should be added when 3063900200092 considering absolute fission yields. 3063900200093 ENDBIB 91 0 3063900200094 COMMON 6 3 3063900200095 EN EN-ERR MONIT MONIT-ERR ASSUM ERR-1 3063900200096 MEV MEV MB MB MB PER-CENT 3063900200097 1.4400E+01 1.9000E-01 1.1760E+02 5.0000E-01 1.1708E+03 3.0 3063900200098 ENDCOMMON 3 0 3063900200099 DATA 7 35 3063900200100 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 3063900200101 FLAG 3063900200102 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3063900200103 NO-DIM 3063900200104 9.1000E+01 3.8000E+01 3.6600E+00 4.0000E-01 1.0000E+003063900200105 3063900200106 9.1000E+01 3.8000E+01 3.3600E+00 5.9000E-01 2.0000E+003063900200107 3063900200108 9.1000E+01 3.8000E+01 4.3700E+00 2.3000E-01 3.0000E+003063900200109 3063900200110 9.1000E+01 3.8000E+01 3.3400E+00 1.8000E-01 4.0000E+003063900200111 2.0000E+00 3063900200112 9.2000E+01 3.8000E+01 3.5200E+00 1.9000E-01 5.0000E+003063900200113 3063900200114 9.5000E+01 4.0000E+01 5.0700E+00 4.9000E-01 6.0000E+003063900200115 2.0000E+00 3063900200116 9.7000E+01 4.0000E+01 5.0200E+00 2.5000E-01 7.0000E+003063900200117 2.0000E+00 3063900200118 9.7000E+01 4.0000E+01 5.4100E+00 2.9000E-01 8.0000E+003063900200119 2.0000E+00 3063900200120 9.9000E+01 4.2000E+01 5.9100E+00 1.2200E+00 9.0000E+003063900200121 3063900200122 9.9000E+01 4.2000E+01 6.0700E+00 3.3000E-01 1.0000E+013063900200123 2.0000E+00 3063900200124 1.0300E+02 4.4000E+01 4.6300E+00 2.6000E-01 1.1000E+013063900200125 3063900200126 1.0500E+02 4.4000E+01 3.4500E+00 1.9000E-01 1.2000E+013063900200127 3063900200128 1.0500E+02 4.5000E+01 0.0000E+00 2.9900E+00 1.9000E-01 1.3000E+013063900200129 1.0000E+00 3063900200130 1.1200E+02 4.6000E+01 1.0230E+00 8.5000E-02 1.4000E+013063900200131 2.0000E+00 3063900200132 1.2700E+02 5.1000E+01 1.4010E+00 1.5500E-01 1.5000E+013063900200133 3063900200134 1.3100E+02 5.3000E+01 4.0800E+00 2.1000E-01 1.6000E+013063900200135 3063900200136 1.3200E+02 5.2000E+01 4.6600E+00 2.7000E-01 1.7000E+013063900200137 3063900200138 1.3200E+02 5.2000E+01 4.4300E+00 3.9000E-01 1.8000E+013063900200139 2.0000E+00 3063900200140 1.3200E+02 5.2000E+01 4.4100E+00 4.0000E-01 1.9000E+013063900200141 2.0000E+00 3063900200142 1.3200E+02 5.2000E+01 4.6500E+00 2.4000E-01 2.0000E+013063900200143 2.0000E+00 3063900200144 1.3200E+02 5.2000E+01 4.5300E+00 2.6000E-01 2.1000E+013063900200145 2.0000E+00 3063900200146 1.3200E+02 5.2000E+01 4.7100E+00 2.6000E-01 2.2000E+013063900200147 2.0000E+00 3063900200148 1.3200E+02 5.2000E+01 4.6000E+00 1.1700E-01 3063900200149 3.0000E+00 3063900200150 1.3300E+02 5.3000E+01 0.0000E+00 6.1300E+00 3.2000E-01 2.3000E+013063900200151 3063900200152 1.3400E+02 5.3000E+01 0.0000E+00 6.3400E+00 8.4000E-01 2.4000E+013063900200153 1.0000E+00 3063900200154 1.3500E+02 5.3000E+01 5.2500E+00 2.9000E-01 2.5000E+013063900200155 3063900200156 1.3500E+02 5.3000E+01 5.0400E+00 2.9000E-01 2.6000E+013063900200157 2.0000E+00 3063900200158 1.3500E+02 5.4000E+01 0.0000E+00 5.3400E+00 3.0000E-01 2.6000E+013063900200159 1.0000E+00 3063900200160 1.4000E+02 5.6000E+01 4.8100E+00 2.9000E-01 2.7000E+013063900200161 3063900200162 1.4000E+02 5.6000E+01 4.8900E+00 2.7000E-01 2.8000E+013063900200163 2.0000E+00 3063900200164 1.4000E+02 5.6000E+01 4.3200E+00 2.2000E-01 2.9000E+013063900200165 2.0000E+00 3063900200166 1.4000E+02 5.6000E+01 4.3900E+00 2.4000E-01 3.0000E+013063900200167 2.0000E+00 3063900200168 1.4000E+02 5.7000E+01 4.4400E+00 3.2000E-01 3.0000E+013063900200169 1.0000E+00 3063900200170 1.4100E+02 5.8000E+01 4.4600E+00 3.0000E-01 3.1000E+013063900200171 3063900200172 1.4300E+02 5.8000E+01 3.6000E+00 1.9000E-01 3.2000E+013063900200173 3063900200174 ENDDATA 74 0 3063900200175 ENDSUBENT 174 0 3063900299999 SUBENT 30639003 20090830 31403063900300001 BIB 12 92 3063900300002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) Short lived products 3063900300003 EXP-YEAR (1971) Second experiment, 2 samples 3063900300004 INC-SOURCE Neutron flux=(2.10+-0.05)*10**8 n/s/cm2 random 3063900300005 error,or +-3% systematic error, 3063900300006 Irradiation time=5 min for each sample 3063900300007 Number of fission events=3.92*10**8 for each sample 3063900300008 SAMPLE 2490.4 grams,thickness=1.47 mm or 921.4 mg/cm**2, 3063900300009 diameter=18.6 mm (both samples) 3063900300010 DETECTOR (GELI).20 cm3, 4000 channel pulse height analyser, 3063900300011 resolution at 662 keV = 4.63 keV. 3063900300012 ANALYSIS 50 gamma spectra were recorded and analysed by an 3063900300013 improved graphical-numerical method using real line 3063900300014 shapes. Complete decay curves from 2.5 minutes to 3063900300015 19.5 days after irradiation were analysed. 3063900300016 DECAY-DATA Parent-daughter relationships indicated by flags 3063900300017 ((1.)34-SE-83-G,22.5MIN,DG,356.6,0.686) 3063900300018 ((2.)36-KR-85-M,4.48HR,DG,151.3,0.761) 3063900300019 ((3.)36-KR-87,76.0MIN,DG,402.7,0.483) 3063900300020 ((4.)36-KR-88,2.80HR,DG,196.1,0.272) 3063900300021 ((5.)36-KR-89,3.16MIN,DG,220.9,0.25) 3063900300022 ((6.)36-KR-89,3.16MIN) for daughter 89Rb 3063900300023 ((6.)37-RB-89,15.2MIN,DG,1031.9,0.641) 3063900300024 ((7.)38-SR-91,9.48HR,DG,1024.3,0.334) 3063900300025 ((8.)38-SR-92,2.71HR,DG,1383.9,0.9) 3063900300026 ((9.)38-SR-93,7.5MIN,DG,590.9,0.61)see flag (4.) 3063900300027 ((10.)40-ZR-97,16.8HR) for daughter 97m,gNb 3063900300028 ((10.)41-NB-97-G,73.6MIN,DG,658.2,0.981) 3063900300029 ((11.)42-MO-101,14.6MIN,DG,590.8,0.194) 3063900300030 ((12.)42-MO-101,14.6MIN) for daughter 101Tc 3063900300031 ((12.)43-TC-101,14.MIN,DG,306.8,0.875) 3063900300032 ((13.)43-TC-104,18.0MIN,DG,357.8,0.844) 3063900300033 ((14.)44-RU-105,4.44HR,DG,724.2,0.49) 3063900300034 ((15.)51-SB-131,23.0MIN) 3063900300035 ((15.)52-TE-131-G,25.0MIN,DG,149.8,0.677) 3063900300036 ((16.)51-SB-131,23.0MIN) 3063900300037 ((16.)52-TE-131-M,30.HR,DG,149.8,0.364) 3063900300038 ((17.)52-TE-132,78.HR,DG,228.2,0.885) 3063900300039 ((18.)52-TE-132,78.HR) for daughter 132I 3063900300040 ((18.)53-I-132-G,2.285HR,DG,667.7,0.980) 3063900300041 ((19.)53-I-133-G,20.8HR,DG,529.5,0.869) 3063900300042 ((20.)52-TE-134,42.MIN,DG,210.8,0.222) 3063900300043 ((21.)52-TE-134,42.MIN) for daughter 134I 3063900300044 ((21.)53-I-134-G,52.6MIN,DG,847.0,0.954)includes 134mI 3063900300045 ((22.)52-TE-134,42.MIN) for daughter 134I 3063900300046 ((22.)53-I-134-G,52.6MIN,DG,884.1,0.653)includes 134mI 3063900300047 ((23.)53-I-134-G,52.6MIN,DG,847.0,0.954)includes 134mI 3063900300048 ((24.)53-I-134-G,52.6MIN,DG,884.1,0.653)includes 134mI 3063900300049 ((25.)53-I-135,6.585HR,DG,1260.5,0.286) 3063900300050 ((26.)53-I-135,6.585HR) for daughter 135Xe 3063900300051 ((26.)54-XE-135-G,9.17HR,DG,249.7,0.903)includes 135mXe3063900300052 ((27.)54-XE-138,14.2MIN) for daughter 138gCs 3063900300053 ((27.)55-CS-138-G,32.2MIN,DG,1435.7,0.750) 3063900300054 ((28.)56-BA-139,83.3MIN,DG,165.8,0.218) 3063900300055 ((29.)57-LA-142,92.4MIN,DG,641.2,0.475) 3063900300056 ((30.)58-CE-143,33.0HR,DG,293.2,0.426) 3063900300057 ((31.)58-CE-146,14.2MIN,DG,218.3,0.214) 3063900300058 ((32.)60-ND-149,1.73HR,DG,211.3,0.23) 3063900300059 MONITOR (29-CU-63(N,2N)29-CU-62,,SIG)using 4-Pi beta counting 3063900300060 MONIT-REF (,Y.KANDA+,C,68WASH,1,193,1968) 3063900300061 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.Sowerby+,AERE-R-7273,19733063900300062 FLAG (1.) For the calculation of the yield of the fission 3063900300063 product given the half-life of its precursor is 3063900300064 also used. 3063900300065 (2.) The yield of the fission product given is derived 3063900300066 from a gamma-line of its daughter product often in3063900300067 equilibrium. 3063900300068 (3.) The weighted average of all yield data for Te-132 3063900300069 listed above this value. 3063900300070 (4.) This is not the value measured in this experiment 3063900300071 for Sr-93, but the cumulative yield of Y-93 from 3063900300072 the 3rd experiment (subentry 4). In this second 3063900300073 experiment the authors obtained a value of 2.51+- 3063900300074 0.23 for the yield of Sr-93, using arbitrarily 1003063900300075 percent intensity of the 590.9 keV gamma-ray in 3063900300076 the decay of Sr-93 (as no absolute intensity value3063900300077 was found in literature). If the abundance of this3063900300078 gamma ray is known, the correct absolute cumu- 3063900300079 lative yield can be calculated using the 'yield' 3063900300080 value given above. From measured yield ratio 3063900300081 Sr-93/Y-93=2.51/4.10=0.61 the authors deduce an 3063900300082 absolute intensity of 61+-8 % for the 590.9 keV 3063900300083 gamma ray of Sr-93. 3063900300084 ERR-ANALYS (DATA-ERR) All errors quoted are one standard deviation3063900300085 They include contributions from: 3063900300086 * peak area and decay curve analysis, 3063900300087 * gamma-ray intensities, 3063900300088 * detector efficiency 3063900300089 * random error of the neutron flux. 3063900300090 Not included is 3063900300091 (ERR-1) the systematic 3% uncertainty in the neutron 3063900300092 flux determination,which should be added when 3063900300093 considering absolute fission yields. 3063900300094 ENDBIB 92 0 3063900300095 COMMON 6 3 3063900300096 EN EN-ERR MONIT MONIT-ERR ASSUM ERR-1 3063900300097 MEV MEV MB MB MB PER-CENT 3063900300098 1.4400E+01 2.5000E-01 4.9700E+02 1.3000E+01 1.1708E+03 3.0 3063900300099 ENDCOMMON 3 0 3063900300100 DATA 7 37 3063900300101 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 3063900300102 FLAG 3063900300103 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3063900300104 NO-DIM 3063900300105 8.3000E+01 3.4000E+01 0.0000E+00 2.6000E-01 5.2000E-02 1.0000E+003063900300106 3063900300107 8.5000E+01 3.6000E+01 1.0000E+00 1.0230E+00 4.6000E-02 2.0000E+003063900300108 3063900300109 8.7000E+01 3.6000E+01 1.8910E+00 8.3000E-02 3.0000E+003063900300110 3063900300111 8.8000E+01 3.6000E+01 1.8260E+00 7.0000E-02 4.0000E+003063900300112 3063900300113 8.9000E+01 3.6000E+01 3.0700E+00 6.4000E-01 5.0000E+003063900300114 3063900300115 8.9000E+01 3.7000E+01 2.8100E+00 1.4000E-01 6.0000E+003063900300116 1.0000E+00 3063900300117 9.1000E+01 3.8000E+01 4.3800E+00 1.5000E-01 7.0000E+003063900300118 3063900300119 9.2000E+01 3.8000E+01 3.8600E+00 1.2000E-01 8.0000E+003063900300120 3063900300121 9.3000E+01 3.8000E+01 4.1000E+00 4.0000E-01 9.0000E+003063900300122 4.0000E+00 3063900300123 9.7000E+01 4.0000E+01 5.0900E+00 1.4000E-01 1.0000E+013063900300124 2.0000E+00 3063900300125 1.0100E+02 4.2000E+01 5.4800E+00 7.3000E-01 1.1000E+013063900300126 3063900300127 1.0100E+02 4.2000E+01 5.7100E+00 2.7000E-01 1.2000E+013063900300128 2.0000E+00 3063900300129 1.0100E+02 4.3000E+01 5.9700E+00 4.1000E-01 1.2000E+013063900300130 1.0000E+00 3063900300131 1.0400E+02 4.3000E+01 3.5900E+00 1.5000E-01 1.3000E+013063900300132 3063900300133 1.0500E+02 4.4000E+01 3.0100E+00 1.3000E-01 1.4000E+013063900300134 3063900300135 1.3100E+02 5.1000E+01 2.5400E+00 1.4000E-01 1.5000E+013063900300136 2.0000E+00 3063900300137 1.3100E+02 5.2000E+01 0.0000E+00 3.8000E+00 1.6000E-01 1.5000E+013063900300138 1.0000E+00 3063900300139 1.3100E+02 5.2000E+01 1.0000E+00 3.1100E-01 1.2500E-01 1.6000E+013063900300140 1.0000E+00 3063900300141 1.3200E+02 5.2000E+01 4.8700E+00 2.1000E-01 1.7000E+013063900300142 3063900300143 1.3200E+02 5.2000E+01 4.5600E+00 1.8000E-01 1.8000E+013063900300144 2.0000E+00 3063900300145 1.3200E+02 5.2000E+01 4.6910E+00 1.3700E-01 3063900300146 3.0000E+00 3063900300147 1.3300E+02 5.3000E+01 6.0000E+00 3.0000E-01 1.9000E+013063900300148 3063900300149 1.3400E+02 5.2000E+01 4.7600E+00 3.1000E-01 2.0000E+013063900300150 3063900300151 1.3400E+02 5.2000E+01 4.4200E+00 1.8000E-01 2.1000E+013063900300152 2.0000E+00 3063900300153 1.3400E+02 5.2000E+01 4.3600E+00 8.0000E-01 2.2000E+013063900300154 2.0000E+00 3063900300155 1.3400E+02 5.3000E+01 0.0000E+00 5.8500E+00 1.8000E-01 2.3000E+013063900300156 3063900300157 1.3400E+02 5.3000E+01 0.0000E+00 5.8900E+00 9.6000E-01 2.4000E+013063900300158 3063900300159 1.3500E+02 5.3000E+01 5.4800E+00 2.2000E-01 2.5000E+013063900300160 3063900300161 1.3500E+02 5.3000E+01 5.3600E+00 2.2000E-01 2.6000E+013063900300162 2.0000E+00 3063900300163 1.3500E+02 5.4000E+01 0.0000E+00 5.6800E+00 2.2000E-01 2.6000E+013063900300164 1.0000E+00 3063900300165 1.3800E+02 5.4000E+01 4.2600E+00 4.4000E-01 2.7000E+013063900300166 2.0000E+00 3063900300167 1.3800E+02 5.5000E+01 0.0000E+00 4.5100E+00 2.3000E-01 2.7000E+013063900300168 1.0000E+00 3063900300169 1.3900E+02 5.6000E+01 5.1300E+00 2.5000E-01 2.8000E+013063900300170 3063900300171 1.4200E+02 5.7000E+01 4.1900E+00 1.4000E-01 2.9000E+013063900300172 3063900300173 1.4300E+02 5.8000E+01 3.9800E+00 1.7000E-01 3.0000E+013063900300174 3063900300175 1.4600E+02 5.8000E+01 1.9190E+00 2.3400E-01 3.1000E+013063900300176 3063900300177 1.4900E+02 6.0000E+01 1.2900E+00 1.3700E-01 3.2000E+013063900300178 3063900300179 ENDDATA 78 0 3063900300180 ENDSUBENT 179 0 3063900399999 SUBENT 30639004 20090830 31403063900400001 BIB 12 94 3063900400002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) Long lived products 3063900400003 EXP-YEAR (1973) Third experiment,repetition of first experiment 3063900400004 with better resolution. 3063900400005 INC-SOURCE Neutron flux=(4.91+-0.11)*10**9 n/s/cm2 random 3063900400006 error,or +-3% systematic error 3063900400007 irradiation time = 1.25 hours 3063900400008 number of fission events = 5.56*10**10. 3063900400009 SAMPLE 996.7 grams, thickness=0.668 mm or 351.5 mg/cm2, 3063900400010 diameter=19.0 mm 3063900400011 DETECTOR (GELI).40 cm3, 4000 channel pulse height analyser, 3063900400012 resolution at 662 keV = 3.36 keV. 3063900400013 ANALYSIS 16 gamma spectra were recorded and analysed by an 3063900400014 improved graphical-numerical method using real line 3063900400015 shapes. Complete decay curves from 41 hrs to 412 days 3063900400016 after irradiation were analysed. 3063900400017 DECAY-DATA Parent-daughter relationships indicated by flags 3063900400018 ((1.)38-SR-91,9.48HR,DG,749.8,0.231) 3063900400019 ((2.)38-SR-91,9.48HR,DG,1024.3,0.334) 3063900400020 ((3.)38-SR-91,9.48HR) for daughter 91mY 3063900400021 ((3.)39-Y-91-M,49.7MIN,DG,555.6,0.558) 3063900400022 ((4.)39-Y-93,10.2HR,DG,267.0,0.064) 3063900400023 ((5.)40-ZR-95,62.5D,DG,724.2,0.438) 3063900400024 ((6.)40-ZR-95,62.5D,DG,756.7,0.544) 3063900400025 ((7.)40-ZR-97,16.8HR) for daughter 97m,gNb 3063900400026 ((7.)41-NB-97-G,73.6MIN,DG,658.2,0.981) 3063900400027 ((8.)40-ZR-97,16.8HR) for daughter 97m,gNb 3063900400028 ((8.)41-NB-97-M,54.SEC,DG,743.4,0.933) 3063900400029 ((9.)42-MO-99,66.02HR,DG,181.0,0.059) 3063900400030 ((10.)42-MO-99,66.02HR,DG,739.6,0.120) 3063900400031 ((11.)42-MO-99,66.02HR) for daughter 99mTc 3063900400032 ((11.)43-TC-99-M,6.02HR,DG,140.4,0.810) 3063900400033 ((12.)44-RU-103,39.6D,DG,497.1,0.89) 3063900400034 ((13.)44-RU-105,4.44HR) for daughter 105m,gRh 3063900400035 ((13.)45-RH-105-G,35.5HR,DG,319.2,0.192)includes 105mRh3063900400036 ((14.)44-RU-106,369.D) 3063900400037 ((14.)45-RH-106-G,,DG,621.8,0.098)equilibrium W. 106Ru 3063900400038 ((15.)46-PD-112,20.1HR) daughter 112Ag measured 3063900400039 ((15.)47-AG-112,3.13HR,DG,617.4,0.429) 3063900400040 ((16.)48-CD-115-G,53.5HR) daughter 115mIn measured 3063900400041 ((16.)49-IN-115-M,4.50HR,DG,336.2,0.470) 3063900400042 ((17.)51-SB-125,3.72YR,DG,427.9,0.304) 3063900400043 ((18.)51-SB-125,3.72YR,DG,600.6,0.181) 3063900400044 ((19.)51-SB-127,3.80D,DG,473.2,0.250) 3063900400045 ((20.)51-SB-127,3.80D,DG,684.9,0.357) 3063900400046 ((21.)52-TE-129-M,33.4D,DG,459.6,0.090) 3063900400047 ((22.)51-SB-131,23.0MIN) 3063900400048 ((22.)52-TE-131-M,30.HR,DG,149.8,0.364) 3063900400049 ((23.)53-I-131,8.041D,DG,364.5,0.820) 3063900400050 ((24.)52-TE-132,78.HR,DG,228.2,0.885) 3063900400051 ((25.)52-TE-132,78.HR) for daughter 132I 3063900400052 ((25.)53-I-132-G,2.285HR,DG,522.6,0.156) 3063900400053 ((26.)52-TE-132,78.HR) for daughter 132I 3063900400054 ((26.)53-I-132-G,2.285HR,DG,630.2,0.135) 3063900400055 ((27.)52-TE-132,78.HR) for daughter 132I 3063900400056 ((27.)53-I-132-G,2.285HR,DG,667.7,0.980) 3063900400057 ((28.)52-TE-132,78.HR) for daughter 132I 3063900400058 ((28.)53-I-132-G,2.285HR,DG,772.7,0.750) 3063900400059 ((29.)52-TE-132,78.HR) for daughter 132I 3063900400060 ((29.)53-I-132-G,2.285HR,DG,954.6,0.167) 3063900400061 ((30.)53-I-133-G,20.8HR,DG,529.5,0.869) 3063900400062 ((31.)53-I-133-G,20.8HR,DG,875.3,0.048) 3063900400063 ((32.)53-I-135,6.585HR) for daughter 135Xe 3063900400064 ((33.)55-CS-137,30.1YR) 3063900400065 ((33.)56-BA-137-M,,DG,661.6,0.85) equilibrium W. 137Cs 3063900400066 ((34.)56-BA-140,12.79D,DG,537.3,0.240) 3063900400067 ((35.)56-BA-140,12.79D) for daughter 140La 3063900400068 ((35.)57-LA-140,40.23HR,DG,815.8,0.223) 3063900400069 ((36.)56-BA-140,12.79D) for daughter 140La 3063900400070 ((36.)57-LA-140,40.23HR,DG,487.0,0.46) 3063900400071 ((37.)58-CE-141,32.53D,DG,145.4,0.48) 3063900400072 ((38.)58-CE-143,33.0HR,DG,293.2,0.426) 3063900400073 ((39.)58-CE-144,284.4D,DG,133.5,0.107) 3063900400074 ((40.)60-ND-147,10.99D,DG,531.0,0.131) 3063900400075 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) using 4-Pi beta counting. 3063900400076 MONIT-REF (,H.VONACH+,J,ZP,237,155,1970) 3063900400077 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.Sowerby+,AERE-R-7273,19733063900400078 FLAG (1.) For the calculation of the yield of the fission 3063900400079 product given the half-life of its precursor is 3063900400080 also used. 3063900400081 (2.) The yield of the fission product given is derived 3063900400082 from a gamma-line of its daughter product often in3063900400083 equilibrium. 3063900400084 (3.) The weighted average of all yield data for Te-132 3063900400085 listed above this value. 3063900400086 ERR-ANALYS (DATA-ERR) All errors quoted are one standard deviation3063900400087 They include contributions from: 3063900400088 * peak area and decay curve analysis, 3063900400089 * gamma-ray intensities, 3063900400090 * detector efficiency 3063900400091 * random error of the neutron flux. 3063900400092 Not included is 3063900400093 (ERR-1) the systematic 3% uncertainty in the neutron 3063900400094 flux determination,which should be added when 3063900400095 considering absolute fission yields. 3063900400096 ENDBIB 94 0 3063900400097 COMMON 6 3 3063900400098 EN EN-ERR MONIT MONIT-ERR ASSUM ERR-1 3063900400099 MEV MEV MB MB MB PER-CENT 3063900400100 1.4540E+01 3.1000E-01 1.1490E+02 5.0000E-01 1.1865E+03 3.0 3063900400101 ENDCOMMON 3 0 3063900400102 DATA 7 41 3063900400103 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 3063900400104 FLAG 3063900400105 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3063900400106 NO-DIM 3063900400107 9.1000E+01 3.8000E+01 4.3900E+00 3.4000E-01 1.0000E+003063900400108 3063900400109 9.1000E+01 3.8000E+01 4.2200E+00 1.5000E-01 2.0000E+003063900400110 3063900400111 9.1000E+01 3.8000E+01 3.7600E+00 1.2000E-01 3.0000E+003063900400112 2.0000E+00 3063900400113 9.3000E+01 3.9000E+01 4.1000E+00 4.0000E-01 4.0000E+003063900400114 3063900400115 9.5000E+01 4.0000E+01 4.6100E+00 1.3000E-01 5.0000E+003063900400116 3063900400117 9.5000E+01 4.0000E+01 4.6300E+00 1.3000E-01 6.0000E+003063900400118 3063900400119 9.7000E+01 4.0000E+01 5.0600E+00 1.6000E-01 7.0000E+003063900400120 2.0000E+00 3063900400121 9.7000E+01 4.0000E+01 5.2900E+00 2.6000E-01 8.0000E+003063900400122 2.0000E+00 3063900400123 9.9000E+01 4.2000E+01 5.8200E+00 2.6000E-01 9.0000E+003063900400124 3063900400125 9.9000E+01 4.2000E+01 5.8000E+00 4.5000E-01 1.0000E+013063900400126 3063900400127 9.9000E+01 4.2000E+01 5.6400E+00 1.7000E-01 1.1000E+013063900400128 2.0000E+00 3063900400129 1.0300E+02 4.4000E+01 4.5100E+00 1.3000E-01 1.2000E+013063900400130 3063900400131 1.0500E+02 4.5000E+01 0.0000E+00 3.1500E+00 1.4000E-01 1.3000E+013063900400132 1.0000E+00 3063900400133 1.0600E+02 4.4000E+01 2.5400E+00 1.5000E-01 1.4000E+013063900400134 2.0000E+00 3063900400135 1.1200E+02 4.6000E+01 1.1100E+00 6.6000E-02 1.5000E+013063900400136 2.0000E+00 3063900400137 1.1500E+02 4.8000E+01 8.4300E-01 4.8000E-02 1.6000E+013063900400138 2.0000E+00 3063900400139 1.2500E+02 5.1000E+01 1.1640E+00 8.3000E-02 1.7000E+013063900400140 3063900400141 1.2500E+02 5.1000E+01 1.3370E+00 1.4900E-01 1.8000E+013063900400142 3063900400143 1.2700E+02 5.1000E+01 1.4130E+00 4.7000E-02 1.9000E+013063900400144 3063900400145 1.2700E+02 5.1000E+01 1.4710E+00 6.9000E-02 2.0000E+013063900400146 3063900400147 1.2900E+02 5.2000E+01 1.0000E+00 5.2600E-01 5.1000E-02 2.1000E+013063900400148 3063900400149 1.3100E+02 5.2000E+01 1.0000E+00 3.6300E-01 3.6000E-02 2.2000E+013063900400150 1.0000E+00 3063900400151 1.3100E+02 5.3000E+01 4.0100E+00 1.1000E-01 2.3000E+013063900400152 3063900400153 1.3200E+02 5.2000E+01 4.6600E+00 1.5000E-01 2.4000E+013063900400154 3063900400155 1.3200E+02 5.2000E+01 4.7700E+00 1.9000E-01 2.5000E+013063900400156 2.0000E+00 3063900400157 1.3200E+02 5.2000E+01 4.6200E+00 1.4000E-01 2.6000E+013063900400158 2.0000E+00 3063900400159 1.3200E+02 5.2000E+01 4.5800E+00 1.8000E-01 2.7000E+013063900400160 2.0000E+00 3063900400161 1.3200E+02 5.2000E+01 4.6400E+00 1.6000E-01 2.8000E+013063900400162 2.0000E+00 3063900400163 1.3200E+02 5.2000E+01 4.6400E+00 1.6000E-01 2.9000E+013063900400164 2.0000E+00 3063900400165 1.3200E+02 5.2000E+01 4.6470E+00 6.6000E-02 3063900400166 3.0000E+00 3063900400167 1.3300E+02 5.3000E+01 5.6500E+00 1.6000E-01 3.0000E+013063900400168 3063900400169 1.3300E+02 5.3000E+01 5.6800E+00 3.5000E-01 3.1000E+013063900400170 3063900400171 1.3500E+02 5.3000E+01 5.1400E+00 2.7000E-01 3.2000E+013063900400172 3063900400173 1.3700E+02 5.5000E+01 5.2100E+00 3.6000E-01 3.3000E+013063900400174 2.0000E+00 3063900400175 1.4000E+02 5.6000E+01 4.7100E+00 1.3000E-01 3.4000E+013063900400176 3063900400177 1.4000E+02 5.6000E+01 4.7900E+00 1.4000E-01 3.5000E+013063900400178 2.0000E+00 3063900400179 1.4000E+02 5.6000E+01 4.4600E+00 1.3000E-01 3.6000E+013063900400180 2.0000E+00 3063900400181 1.4100E+02 5.8000E+01 4.3600E+00 1.6000E-01 3.7000E+013063900400182 3063900400183 1.4300E+02 5.8000E+01 3.8800E+00 1.2000E-01 3.8000E+013063900400184 3063900400185 1.4400E+02 5.8000E+01 3.3900E+00 2.2000E-01 3.9000E+013063900400186 3063900400187 1.4700E+02 6.0000E+01 2.3000E+00 1.0000E-01 4.0000E+013063900400188 3063900400189 ENDDATA 86 0 3063900400190 ENDSUBENT 189 0 3063900499999 SUBENT 30639005 20090830 31403063900500001 BIB 5 32 3063900500002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) Final result of all 3 3063900500003 experiments 3063900500004 REL-REF (N,,M.E.Meek+,R,NEDO-12154-1,1974) 3063900500005 Data for charge distribution and decay branching ratios3063900500006 used in the analysis are taken from M.E.Meek and 3063900500007 B.F.Rider,NEDO-12154-1,1974. 3063900500008 FLAG (1.) Individual results for parent and daughter are 3063900500009 averaged together as charge distribution indicates3063900500010 zero independent yield for daughter. 3063900500011 (2.) Included in the average cumulative yield of I-131 3063900500012 is a value of 4.09+-0.17 derived from the sum of 3063900500013 the cumulative yield of Sb-131(listed above) and 3063900500014 the independent yields of the Te-131 isomers 3063900500015 (subentry 9) 3063900500016 (3.) For Te-132,the yield value given here is derived 3063900500017 from the weighted averages obtained in each 3063900500018 experiment (identified by flag 3. in subentries 3063900500019 2,3 and 4). 3063900500020 (4.) A value calculated as cumulative yield of parent 3063900500021 plus independent yield of product (derived from 3063900500022 charge distribution) is included in the average. 3063900500023 STATUS (DEP,30639002) and 3063900500024 (DEP,30639003) and 3063900500025 (DEP,30639004) as weighted average of all individual 3063900500026 results of the 3 experiments compiled in the 3063900500027 previous subentries. 3063900500028 ERR-ANALYS (DATA-ERR) The errors are one standard deviation 3063900500029 calculated from the errors of individual measurements 3063900500030 as compiled in the preceding subentries. 3063900500031 (ERR-1) For the total error of absolute yields a 3% 3063900500032 systematic uncertainty in the neutron flux 3063900500033 determination has to be added. 3063900500034 ENDBIB 32 0 3063900500035 COMMON 3 3 3063900500036 EN-MIN EN-MAX ERR-1 3063900500037 MEV MEV PER-CENT 3063900500038 1.4400E+01 1.4520E+01 3.0 3063900500039 ENDCOMMON 3 0 3063900500040 DATA 6 47 3063900500041 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 3063900500042 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3063900500043 8.3000E+01 3.4000E+01 0.0000E+00 2.6000E-01 5.2000E-02 3063900500044 8.5000E+01 3.6000E+01 1.0000E+00 1.0230E+00 4.6000E-02 3063900500045 8.7000E+01 3.6000E+01 1.8910E+00 8.3000E-02 3063900500046 8.8000E+01 3.6000E+01 1.8260E+00 7.0000E-02 3063900500047 8.9000E+01 3.6000E+01 3.0700E+00 6.4000E-01 3063900500048 8.9000E+01 3.7000E+01 2.8100E+00 1.4000E-01 3063900500049 9.1000E+01 3.8000E+01 3.9800E+00 1.6000E-01 3063900500050 9.2000E+01 3.8000E+01 3.7800E+00 1.0000E-01 3063900500051 9.3000E+01 3.9000E+01 4.1000E+00 4.0000E-01 3063900500052 9.5000E+01 4.0000E+01 4.6400E+00 9.0000E-02 3063900500053 9.7000E+01 4.0000E+01 5.1200E+00 9.0000E-02 3063900500054 9.9000E+01 4.2000E+01 5.7600E+00 1.2000E-01 3063900500055 1.0100E+02 4.2000E+01 5.7600E+00 2.2000E-01 1.0000E+003063900500056 1.0100E+02 4.3000E+01 5.7600E+00 2.2000E-01 1.0000E+003063900500057 1.0300E+02 4.4000E+01 4.5300E+00 1.2000E-01 3063900500058 1.0400E+02 4.3000E+01 3.5900E+00 1.5000E-01 3063900500059 1.0500E+02 4.4000E+01 3.1200E+00 8.0000E-02 1.0000E+003063900500060 1.0500E+02 4.5000E+01 3.1200E+00 8.0000E-02 1.0000E+003063900500061 1.0600E+02 4.4000E+01 2.5400E+00 1.5000E-01 3063900500062 1.1200E+02 4.6000E+01 1.0770E+00 5.2000E-02 3063900500063 1.1500E+02 4.8000E+01 0.0000E+00 8.4300E-01 4.8000E-02 3063900500064 1.2500E+02 5.1000E+01 1.2050E+00 7.3000E-02 3063900500065 1.2700E+02 5.1000E+01 1.4300E+00 3.8000E-02 3063900500066 1.2900E+02 5.2000E+01 1.0000E+00 5.2600E-01 5.1000E-02 3063900500067 1.3100E+02 5.1000E+01 2.5400E+00 1.4000E-01 3063900500068 1.3100E+02 5.2000E+01 0.0000E+00 3.8000E+00 1.6000E-01 3063900500069 1.3100E+02 5.2000E+01 1.0000E+00 3.5900E-01 3.5000E-02 3063900500070 1.3100E+02 5.3000E+01 4.0400E+00 8.0000E-02 2.0000E+003063900500071 1.3200E+02 5.2000E+01 4.6440E+00 5.3000E-02 3.0000E+003063900500072 1.3300E+02 5.3000E+01 0.0000E+00 5.7800E+00 1.2000E-01 3063900500073 1.3400E+02 5.2000E+01 4.5000E+00 1.5000E-01 3063900500074 1.3400E+02 5.3000E+01 5.8900E+00 1.6000E-01 4.0000E+003063900500075 1.3500E+02 5.3000E+01 5.2900E+00 1.1000E-01 3063900500076 1.3500E+02 5.4000E+01 5.5800E+00 1.5000E-01 4.0000E+003063900500077 1.3700E+02 5.5000E+01 5.2100E+00 3.6000E-01 3063900500078 1.3800E+02 5.4000E+01 4.2600E+00 4.4000E-01 3063900500079 1.3800E+02 5.5000E+01 0.0000E+00 4.5300E+00 2.2000E-01 4.0000E+003063900500080 1.3900E+02 5.6000E+01 5.1300E+00 2.5000E-01 3063900500081 1.4000E+02 5.6000E+01 4.6200E+00 7.0000E-02 3063900500082 1.4000E+02 5.7000E+01 4.6300E+00 7.0000E-02 4.0000E+003063900500083 1.4100E+02 5.8000E+01 4.3800E+00 1.4000E-01 3063900500084 1.4200E+02 5.7000E+01 4.1900E+00 1.4000E-01 3063900500085 1.4300E+02 5.8000E+01 3.8500E+00 9.0000E-02 3063900500086 1.4400E+02 5.8000E+01 3.3900E+00 2.2000E-01 3063900500087 1.4600E+02 5.8000E+01 1.9190E+00 2.3400E-01 3063900500088 1.4700E+02 6.0000E+01 2.3000E+00 1.0000E-01 3063900500089 1.4900E+02 6.0000E+01 1.2900E+00 1.3700E-01 3063900500090 ENDDATA 49 0 3063900500091 ENDSUBENT 90 0 3063900599999 SUBENT 30639006 20090830 31403063900600001 BIB 7 30 3063900600002 REACTION (92-U-238(N,F)MASS,CHN,FY) 3063900600003 REL-REF (N,,M.E.Meek+,R,NEDO-12154-1,1974) See METHOD below 3063900600004 METHOD Chain yields are deduced using charge distribution data3063900600005 and branching ratios for the formation of the measured 3063900600006 nuclides from beta decay of their precursors (both 3063900600007 taken from M.E.Meek and B.F.Rider,NEDO-12154-1,1974). 3063900600008 Compilers note: For those 3 cases where the chain 3063900600009 yield was deduced using (only) branching ratios (see 3063900600010 'MISC'-column and 'FLAG'),the data given by Meek and 3063900600011 Rider indicate that direct yields of the nuclides 3063900600012 measured or their isomers can be neglected within the 3063900600013 error limits of the experiment. 3063900600014 MISC-COL (MISC) Decay branching ratio used (see 'METHOD') 3063900600015 FLAG Flags are only given for chain yield values differing 3063900600016 from the cumulative yields from which they were deduced3063900600017 (1.) Deduced using branching ratio (value under 'MISC')3063900600018 (2.) Deduced using charge distribution data 3063900600019 STATUS (DEP,30639005)As the weighted average of 3063900600020 measured cumulative yields. 3063900600021 ERR-ANALYS (DATA-ERR) The errors are one standard deviation and 3063900600022 (relative) the same as those of the cumulative 3063900600023 yields from which the data were derived. 3063900600024 (ERR-1) For the total error of absolute yields a 3% 3063900600025 systematic uncertainty in the neutron flux 3063900600026 determination has to be added. 3063900600027 Compilers note: Uncertainties in the branching ratios 3063900600028 and charge distribution data used for calculating chain3063900600029 yields from measured yields are not taken into account.3063900600030 The uncertainty contribution from charge distribution 3063900600031 data is significant only for masses 132 and 138. 3063900600032 ENDBIB 30 0 3063900600033 COMMON 3 3 3063900600034 EN-MIN EN-MAX ERR-1 3063900600035 MEV MEV PER-CENT 3063900600036 1.4400E+01 1.4520E+01 3.0 3063900600037 ENDCOMMON 3 0 3063900600038 DATA 5 37 3063900600039 MASS DATA DATA-ERR FLAG MISC 3063900600040 NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM 3063900600041 8.3000E+01 7.2200E-01 1.4400E-01 1.0000E+00 3.6000E-01 3063900600042 8.5000E+01 1.0230E+00 4.6000E-02 3063900600043 8.7000E+01 1.8910E+00 8.3000E-02 3063900600044 8.8000E+01 1.8290E+00 7.0000E-02 2.0000E+00 3063900600045 8.9000E+01 2.8300E+00 1.4000E-01 2.0000E+00 3063900600046 9.1000E+01 3.9800E+00 1.6000E-01 3063900600047 9.2000E+01 3.7800E+00 1.0000E-01 3063900600048 9.3000E+01 4.1000E+00 4.0000E-01 3063900600049 9.5000E+01 4.6400E+00 9.0000E-02 3063900600050 9.7000E+01 5.1200E+00 9.0000E-02 3063900600051 9.9000E+01 5.7600E+00 1.2000E-01 3063900600052 1.0100E+02 5.7600E+00 2.2000E-01 3063900600053 1.0300E+02 4.5300E+00 1.2000E-01 3063900600054 1.0400E+02 3.5900E+00 1.5000E-01 3063900600055 1.0500E+02 3.1200E+00 8.0000E-02 3063900600056 1.0600E+02 2.5400E+00 1.5000E-01 3063900600057 1.1200E+02 1.0770E+00 5.2000E-02 3063900600058 1.1500E+02 9.7500E-01 5.5000E-02 1.0000E+00 8.6500E-01 3063900600059 1.2500E+02 1.2050E+00 7.3000E-02 3063900600060 1.2700E+02 1.4310E+00 3.8000E-02 2.0000E+00 3063900600061 1.2900E+02 3.1700E+00 3.1000E-01 1.0000E+00 1.6600E-01 3063900600062 1.3100E+02 4.0400E+00 8.0000E-02 3063900600063 1.3200E+02 4.8200E+00 6.0000E-02 2.0000E+00 3063900600064 1.3300E+02 5.8000E+00 1.2000E-01 2.0000E+00 3063900600065 1.3400E+02 5.9500E+00 1.6000E-01 2.0000E+00 3063900600066 1.3500E+02 5.5800E+00 1.5000E-01 3063900600067 1.3700E+02 5.2100E+00 3.6000E-01 3063900600068 1.3800E+02 4.6100E+00 2.2000E-01 2.0000E+00 3063900600069 1.3900E+02 5.1300E+00 2.5000E-01 3063900600070 1.4000E+02 4.6300E+00 7.0000E-02 3063900600071 1.4100E+02 4.3800E+00 1.4000E-01 3063900600072 1.4200E+02 4.1900E+00 1.4000E-01 3063900600073 1.4300E+02 3.8500E+00 9.0000E-02 3063900600074 1.4400E+02 3.3900E+00 2.2000E-01 3063900600075 1.4600E+02 1.9250E+00 2.3500E-01 2.0000E+00 3063900600076 1.4700E+02 2.3000E+00 1.0000E-01 3063900600077 1.4900E+02 1.2900E+00 1.3700E-01 3063900600078 ENDDATA 39 0 3063900600079 ENDSUBENT 78 0 3063900699999 SUBENT 30639007 20090830 31403063900700001 BIB 13 35 3063900700002 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) Long lived products 3063900700003 EXP-YEAR (1969) First experiment 3063900700004 INC-SOURCE Neutron flux=(7.80+-0.36)*10**6 n/s/cm2 random 3063900700005 error,or +-3% systematic error 3063900700006 Irradiation time=29.25 hours 3063900700007 Number of fission events = 5.41*10**9 3063900700008 SAMPLE 2640 grams,thickness=1.47 mm or 921.4 mg/cm2, 3063900700009 diameter=19.1 mm. 3063900700010 DETECTOR (GELI).27 cm3, 4000 channel pulse height analyser, 3063900700011 resolution at 662 keV = 7.3 keV. 3063900700012 ANALYSIS (DECAY). Deduced from measured gamma-spectra of the 3063900700013 nuclide listed and its parent. 3063900700014 DECAY-DATA For calculation of the independent yield of the product3063900700015 listed the half-life of its precursor (Z-1) is also 3063900700016 used. 3063900700017 ((1.)53-I-135,6.585HR) 3063900700018 ((1.)54-XE-135-G,9.17HR,DG,249.7,0.903) incl. Xe-135m 3063900700019 ((2.)56-BA-140,12.79D) 3063900700020 ((2.)57-LA-140,40.23HR,DG,487.0,0.46) 3063900700021 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) Measured with Ge(Li) det. 3063900700022 MONIT-REF (,H.VONACH+,J,ZP,237,155,1970) 3063900700023 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.Sowerby+,AERE-R-7273,19733063900700024 FLAG (1.) Yield for both isomers. The half-life of the 3063900700025 metastable state is neglected. 3063900700026 STATUS (DEP,30639002) The same raw data are used 3063900700027 ERR-ANALYS (DATA-ERR) All errors quoted are one standard 3063900700028 deviation. They include contributions from 3063900700029 * peak area and decay curve analysis, 3063900700030 * gamma-ray intensities, 3063900700031 * detector efficiency 3063900700032 * random error of the neutron flux. 3063900700033 Not included is 3063900700034 (ERR-1) the systematic 3% uncertainty in the neutron 3063900700035 flux determination,which should be added when 3063900700036 considering absolute fission yields. 3063900700037 ENDBIB 35 0 3063900700038 COMMON 6 3 3063900700039 EN EN-ERR MONIT MONIT-ERR ASSUM ERR-1 3063900700040 MEV MEV MB MB MB PER-CENT 3063900700041 1.4400E+01 1.9000E-01 1.1760E+02 5.0000E-01 1.1708E+03 3.0 3063900700042 ENDCOMMON 3 0 3063900700043 DATA 6 2 3063900700044 MASS ELEMENT DATA DATA-ERR DECAY-FLAG FLAG 3063900700045 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM 3063900700046 1.3500E+02 5.4000E+01 2.9900E-01 1.0600E-01 1.0000E+00 1.0000E+003063900700047 1.4000E+02 5.7000E+01 4.6000E-02 5.0000E-02 2.0000E+00 3063900700048 ENDDATA 4 0 3063900700049 ENDSUBENT 48 0 3063900799999 SUBENT 30639008 20090830 31403063900800001 BIB 13 55 3063900800002 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) Short lived products 3063900800003 EXP-YEAR (1971) Second experiment, 2 samples 3063900800004 INC-SOURCE Neutron flux=(2.10+-0.05)*10**8 n/s/cm2 random 3063900800005 error,or +-3% systematic error, 3063900800006 Irradiation time=5 min for each sample 3063900800007 Number of fission events=3.92*10**8 for each sample3063900800008 SAMPLE 2490.4 grams,thickness=1.47 mm or 921.4 mg/cm2, 3063900800009 diameter=18.6 mm (both samples) 3063900800010 DETECTOR (GELI).20 cm3, 4000 channel pulse height analyser, 3063900800011 resolution at 662 keV = 4.63 keV. 3063900800012 ANALYSIS (DECAY).Deduced from measured gamma-spectra of the 3063900800013 nuclide listed and its parent. 3063900800014 DECAY-DATA For calculation of the independent yield of the product3063900800015 listed the half-life of its precursor (Z-1) is also 3063900800016 used. If the sum of yields for both isomers is given, 3063900800017 a decay flag for the short lived metastable state 3063900800018 (generally neglected) is not included. 3063900800019 ((1.)42-MO-101,14.6MIN) for daughter 101Tc 3063900800020 ((1.)43-TC-101,14.MIN,DG,306.8,0.875) 3063900800021 ((2.)51-SB-131,23.0MIN) 3063900800022 ((2.)52-TE-131-G,25.0MIN,DG,149.8,0.677) 3063900800023 ((3.)51-SB-131,23.0MIN) 3063900800024 ((3.)52-TE-131-G,25.0MIN,DG,149.8,0.677) 3063900800025 ((3.)52-TE-131-M,30.HR,DG,149.8,0.364) 3063900800026 ((4.)52-TE-134,42.MIN) for daughter 134I 3063900800027 ((4.)53-I-134-G,52.6MIN,DG,847.0,0.954)includes 134mI 3063900800028 ((5.)52-TE-134,42.MIN) for daughter I-134 3063900800029 ((5.)53-I-134-G,52.6MIN,DG,884.1,0.653)includes 134mI 3063900800030 ((6.)53-I-135,6.585HR) for daughter Xe-135 3063900800031 ((6.)54-XE-135-G,9.17HR,DG,249.7,0.903) incl. 135mXe 3063900800032 ((7.)54-XE-138,14.2MIN) for daughter 138gCs 3063900800033 ((7.)55-CS-138-G,32.2MIN,DG,1435.7,0.750) 3063900800034 MONITOR (29-CU-63(N,2N)29-CU-62,,SIG)Using 4-Pi beta counting 3063900800035 MONIT-REF (,Y.KANDA+,C,68WASH,1,193,1968) 3063900800036 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.Sowerby+,AERE-R-7273,19733063900800037 FLAG (1.) Decay branching ratios are taken from H.E.Meek and3063900800038 B.F.Rider,NEDO-12154-1,1974. Te-131m contributes 3063900800039 only little to this yield value and its Decay-Flag3063900800040 (48.) is not included in this line. 3063900800041 (2.) Sum yield for both isomers. 3063900800042 Decay branching ratios are taken from Meek and 3063900800043 Rider (see Flag 1.). 3063900800044 (3.) Sum yield for both isomers, deduced from ground 3063900800045 state decay. 3063900800046 STATUS (DEP,30639003) The same raw data are used 3063900800047 ERR-ANALYS (DATA-ERR) All errors quoted are one standard 3063900800048 deviation. They include contributions from 3063900800049 * peak area and decay curve analysis, 3063900800050 * gamma-ray intensities, 3063900800051 * detector efficiency 3063900800052 * random error of the neutron flux. 3063900800053 Not included is 3063900800054 (ERR-1) the systematic 3% uncertainty in the neutron 3063900800055 flux determination,which should be added when 3063900800056 considering absolute fission yields. 3063900800057 ENDBIB 55 0 3063900800058 COMMON 6 3 3063900800059 EN EN-ERR MONIT MONIT-ERR ASSUM ERR-1 3063900800060 MEV MEV MB MB MB PER-CENT 3063900800061 1.4400E+01 1.9000E-01 4.9700E+02 1.3000E+01 1.1708E+03 3.0 3063900800062 ENDCOMMON 3 0 3063900800063 DATA 7 7 3063900800064 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 3063900800065 FLAG 3063900800066 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3063900800067 NO-DIM 3063900800068 1.0100E+02 4.3000E+01 2.6800E-01 5.7700E-01 1.0000E+003063900800069 3063900800070 1.3100E+02 5.2000E+01 0.0000E+00 1.3770E+00 2.0800E-01 2.0000E+003063900800071 1.0000E+00 3063900800072 1.3100E+02 5.2000E+01 1.5580E+00 2.1100E-01 3.0000E+003063900800073 2.0000E+00 3063900800074 1.3400E+02 5.3000E+01 1.4290E+00 2.1300E-01 4.0000E+003063900800075 3.0000E+00 3063900800076 1.3400E+02 5.3000E+01 1.5350E+00 1.7030E+00 5.0000E+003063900800077 3.0000E+00 3063900800078 1.3500E+02 5.4000E+01 3.1900E-01 7.8000E-02 6.0000E+003063900800079 3.0000E+00 3063900800080 1.3800E+02 5.5000E+01 0.0000E+00 2.4600E-01 5.8300E-01 7.0000E+003063900800081 3063900800082 ENDDATA 18 0 3063900800083 ENDSUBENT 82 0 3063900899999 SUBENT 30639009 20090830 31403063900900001 BIB 4 22 3063900900002 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) Combined results 3063900900003 FLAG (1.)The authors state in a footnote to Table III, that 3063900900004 the Te-131m independent yield was deduced from the 3063900900005 cumulative yields of Sb-131 and Te-131m,using decay3063900900006 branching ratios from M.E.Meek and B.F.Rider, 3063900900007 NEDO-12154-1,1974. 3063900900008 Compilers comment: Since the independent yields of 3063900900009 Te-131m and Te-131g add up exactly to the combined 3063900900010 yield given for both isomers (as in subentry 8), it 3063900900011 seems that all independent and cumulative yield data 3063900900012 for mass=131 (except I-131) have been obtained in a 3063900900013 combined decay curve analysis from the 2nd experiment 3063900900014 (2.) yield for both isomers.For Te-131 see also flag 1.3063900900015 STATUS (DEP,30639007) and 3063900900016 (DEP,30639008) as weighted average of individual 3063900900017 results of both experiments. 3063900900018 ERR-ANALYS (DATA-ERR) The errors are one standard deviation 3063900900019 calculated from the errors of individual measurements3063900900020 as compiled in the preceding subentries. 3063900900021 (ERR-1) For the total error of absolute yields a 3% 3063900900022 systematic uncertainty in the neutron flux 3063900900023 determination has to be added. 3063900900024 ENDBIB 22 0 3063900900025 COMMON 2 3 3063900900026 EN ERR-1 3063900900027 MEV PER-CENT 3063900900028 1.4400E+01 3. 3063900900029 ENDCOMMON 3 0 3063900900030 DATA 6 8 3063900900031 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 3063900900032 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3063900900033 1.0100E+02 4.3000E+01 2.6800E-01 5.7700E-01 3063900900034 1.3100E+02 5.2000E+01 1.0000E+00 1.8100E-01 3.6000E-02 1.0000E+003063900900035 1.3100E+02 5.2000E+01 0.0000E+00 1.3770E+00 2.0800E-01 1.0000E+003063900900036 1.3100E+02 5.2000E+01 1.5580E+00 2.1100E-01 2.0000E+003063900900037 1.3400E+02 5.3000E+01 1.4310E+00 2.1100E-01 2.0000E+003063900900038 1.3500E+02 5.4000E+01 3.1200E-01 6.3000E-02 2.0000E+003063900900039 1.3800E+02 5.5000E+01 0.0000E+00 2.4600E-01 5.8300E-01 3063900900040 1.4000E+02 5.7000E+01 4.6000E-02 5.0000E-02 3063900900041 ENDDATA 10 0 3063900900042 ENDSUBENT 41 0 3063900999999 SUBENT 30639010 20090830 31403063901000001 BIB 4 11 3063901000002 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 3063901000003 (92-U-238(N,F)MASS,CHN,FY))Fractional independent yield3063901000004 RESULT (FRIND) 3063901000005 FLAG (1.) Sum yields for both isomers 3063901000006 STATUS (DEP,30639009) Independent yields, divided by 3063901000007 (DEP,30639006) total chain yields. 3063901000008 representing the combined errors of 3063901000009 independent and chain yields. 3063901000010 Compilers comment = the 3% systematic error of 3063901000011 the neutron flux cancels in the ratio and must not Be 3063901000012 included in the total error. 3063901000013 ENDBIB 11 0 3063901000014 COMMON 1 3 3063901000015 EN 3063901000016 MEV 3063901000017 1.4400E+01 3063901000018 ENDCOMMON 3 0 3063901000019 DATA 6 6 3063901000020 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 3063901000021 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 3063901000022 1.0100E+02 4.3000E+01 4.5000E-02 9.7000E-02 3063901000023 1.3100E+02 5.2000E+01 3.8600E-01 5.3000E-02 1.0000E+003063901000024 1.3400E+02 5.3000E+01 2.4200E-01 3.7000E-02 1.0000E+003063901000025 1.3500E+02 5.4000E+01 5.6000E-02 1.2000E-02 1.0000E+003063901000026 1.3800E+02 5.5000E+01 0.0000E+00 5.4000E-02 1.2700E-01 3063901000027 1.4000E+02 5.7000E+01 1.0000E-02 1.1000E-02 3063901000028 ENDDATA 8 0 3063901000029 ENDSUBENT 28 0 3063901099999 ENDENTRY 10 0 3063999999999