ENTRY 31538 20211005 32023153800000001 SUBENT 31538001 20211005 32023153800100001 BIB 9 90 3153800100002 TITLE Measurement of Absolute Fission Yields in the Fast 3153800100003 Neutron-Induced Fission of Actinides: 3153800100004 238U, 237Np, 238Pu, 240Pu, 243Am, and 244Cm by 3153800100005 Track-Etch-cum-Gamma Spectrometry 3153800100006 AUTHOR (R.H.Iyer,H.Naik,A.K.Pandey,P.C.Kalsi,R.J.Singh, 3153800100007 A.Ramaswami,A.G.C.Nair) 3153800100008 INSTITUTE (3INDTRM) 3153800100009 REFERENCE (J,NSE,135,227,2000) 3153800100010 (J,RM,27,529,1997) The data for 240Pu and 241Am 3153800100011 were published. 3153800100012 (J,RCA,75,69,1996) part of the data on the fast 3153800100013 neutron-induced fission of 238U has been published. 3153800100014 A preliminary report of this work has been published 3153800100015 in Proc. Int. Seminar Enhanced Utilization 3153800100016 and Reactors, Bombay, India, March 11-15, 1996 3153800100017 DETECTOR (TRD) Lexa or mica strip for collection of fission 3153800100018 products 3153800100019 (HPGE) The products were analyzed by gamma spectrometry3153800100020 at a fixed geometry of an energy- and efficiency- 3153800100021 calibrated 80- or 120-cm3 high-purity germanium 3153800100022 detector coupled to a PC-based 4K channel analyzer. 3153800100023 (SIBAR) The purity of the targets and the amounts were 3153800100024 assayed and checked by alpha spectrometry using a 3153800100025 silicon surface barrier detector connected to a 3153800100026 PC-based 4K. channel analyzer. 3153800100027 ANALYSIS The targets were covered with 0.75-mu-m-thick superpure3153800100028 aluminum foil and then with a 75-mu-m-thick Lexan foil,3153800100029 which acted as a catcher foil to collect the recoiling 3153800100030 fission products during neutron irradiation of the 3153800100031 target. The thin aluminum foil prevented self-transfer 3153800100032 of the target activity to the Lexan catcher foil. It 3153800100033 was then wrapped with another piece of 0.0025-cm-thick 3153800100034 aluminum foil. About 200 mu-l of a dilute solution of 3153800100035 known concentration of 238U (1.42 mg/ml), 3153800100036 237Np (24.56 mu-g/ml), 238Pu (0.50 mu-g/ml), 3153800100037 240Pu (5.07 mu-g/ml), 243Am (26.85 mu-g/ml), and 3153800100038 244Cm (0.202 mu-g/ml) were taken in polypropylene tubes3153800100039 approx.4 cm long and with a 3-mm inner diameter with an3153800100040 open cut at one end. Two small strips of mica or Lexan 3153800100041 track detectors were put into the solution, and the 3153800100042 polypropylene tubes were then heat sealed. The targets 3153800100043 and the sealed polypropylene tubes were wrapped with 3153800100044 1-mm-thick cadmium foils and then double sealed in 3153800100045 alkathene bags. 3153800100046 For short-lived fission products in the case of 238U 3153800100047 and 237Np, approx. 200 ml of 238U (30.01 mg/ml) and 3153800100048 237Np (1.228 mg/ml) in the form of nitrate solutions 3153800100049 along with a strip of Lexan or mica track detector seal3153800100050 in a polypropylene tube were covered with 1-mm-thick 3153800100051 cadmium foil and again sealed in alkathene bags. 3153800100052 METHOD (ACTIV,CHSEP) The absolute fission yields of various 3153800100053 fission products were determined using radiochemical 3153800100054 and gamma spectrometric techniques in combination with 3153800100055 the track-etch method. 3153800100056 ERR-ANALYS (ERR-SYS) Systematic errors due to uncertainties in: 3153800100057 (ERR-1) the irradiation time (2%); 3153800100058 (ERR-2) detector efficiency calibration (3%); 3153800100059 (ERR-3) half-lives of fission products (1%); 3153800100060 and gamma-ray abundance, which shows the largest 3153800100061 variation in the literature. 3153800100062 (ERR-S,6.,7.) The random error in the observed 3153800100063 activity due to: 3153800100064 (ERR-4,,5.) counting statistics, determined by 3153800100065 accumulating the data for optimum time periods, is 3153800100066 estimated to be less than 5%, depending on the 3153800100067 half-life of the nuclide of interest. 3153800100068 The random error in the calculation of the 3153800100069 total number of fissions, which can arise from the 3153800100070 uncertainties in the measurement of: 3153800100071 (ERR-5) the track density (3%), 3153800100072 (ERR-6) track registration efficiency (1%), 3153800100073 (ERR-7) the weight (amount) of the fissile material in 3153800100074 the target and in the dilute solution (0.5%). 3153800100075 Besides these, one additional source of random error of3153800100076 3% is estimated in the chemical yield determination 3153800100077 in the case of the radiochemically separated samples. 3153800100078 HISTORY (20040121C) SD 3153800100079 (20050221A) SD. Added reference 3153800100080 (20080527A) SD. Data headings in Subents 009-014 were 3153800100081 changed from PC/FIS on PRT/FIS. 3153800100082 (20080826A) SD,NO. Energy changed on 1.9 from 1. MeV 3153800100083 and in Subents 002-014 added FIS in SF8 reaction code. 3153800100084 (20090819A) SD: duplicate keyword INC-SPECT from 3153800100085 Subent 008 was deleted. 3153800100086 (20210923A) VS. EN-DUMMY=1.9 MeV -> EN-MIN=0.5 eV and 3153800100087 SF8:FIS->EPI and ERR-S -> DARA-ERR in 002-014; 3153800100088 ERR-ANALYS corrected and moved from 001 to 002-008 3153800100089 and added in 009-014. 3153800100090 STATUS moved from 001 to 002-014. 3153800100091 DECAY-DATA moved from 001 to 002-008. 3153800100092 ENDBIB 90 0 3153800100093 COMMON 8 6 3153800100094 EN-MIN ERR-SYS ERR-1 ERR-2 ERR-3 ERR-5 3153800100095 ERR-6 ERR-7 3153800100096 EV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3153800100097 PER-CENT PER-CENT 3153800100098 0.5 4. 2. 3. 1. 3. 3153800100099 1. 0.5 3153800100100 ENDCOMMON 6 0 3153800100101 ENDSUBENT 100 0 3153800199999 SUBENT 31538002 20211006 32023153800200001 BIB 8 70 3153800200002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,EPI) 3153800200003 INC-SPECT Epi-cadmium spectrum 3153800200004 FACILITY (REAC,3INDTRM) The target assemblies were irradiated 3153800200005 for 30 min to 7 hr in a fixed water-moderated, highly 3153800200006 enriched uranium-fueled swimming pool reactor APSARA 3153800200007 at a flux of 10**11 n/cm2/s. 3153800200008 For short-lived fission products the U target was 3153800200009 irradiated for 5 min in the same position. 3153800200010 SAMPLE A known amount (approx.5 mg) of the oxide of 238U 3153800200011 of purity 99.9997% was carefully weighed into a small 3153800200012 piece (1 cm X 1 cm) of 0.0025-cm-thick superpure 3153800200013 aluminum foil and folded into a small packet. 3153800200014 DECAY-DATA ((1.)35-BR-83,2.39HR,DG,529.5,0.013) 3153800200015 ((2.)36-KR-85-M,4.48HR,DG,304.9,0.137) 3153800200016 ((3.)36-KR-87,76.3MIN,DG,402.6,0.496) 3153800200017 ((4.)36-KR-88,2.84HR,DG,196.3,0.263) 3153800200018 ((5.)37-RB-89,15.2MIN,DG,1032.1,0.58) 3153800200019 ((6.)37-RB-89,15.2MIN,DG,1248.1,0.426) 3153800200020 ((7.)38-SR-91,9.52HR,DG,1024.3,0.334) 3153800200021 ((8.)38-SR-92,2.71HR,DG,1384.1,0.90) 3153800200022 ((9.)38-SR-93,7.42MIN,DG,875.9,0.239) 3153800200023 ((11.)39-Y-93-G,10.25HR,DG,266.9,0.068) 3153800200024 ((12.)39-Y-94,18.7MIN,DG,918.7,0.56) 3153800200025 ((13.)39-Y-95,10.3MIN,DG,954.1,0.134) 3153800200026 ((14.)40-ZR-95,64.02D,DG,756.7,0.545) 3153800200027 ((15.)40-ZR-97,16.9HR,DG,743.3,0.928) 3153800200028 ((16.)42-MO-99,2.748D,DG,140.5,0.907) 3153800200029 ((17.)42-MO-99,2.748D,DG,739.4,0.121) 3153800200030 ((18.)42-MO-101,14.6MIN,DG,590.9,0.164) 3153800200031 ((19.)43-TC-104,18.3MIN,DG,358.0,0.89) 3153800200032 ((21.)44-RU-103,39.254D,DG,497.1,0.887) 3153800200033 ((22.)44-RU-105,4.44HR,DG,724.3,0.467) 3153800200034 ((25.)45-RH-107,21.7MIN,DG,302.8,0.66) 3153800200035 ((26.)47-AG-111-G,7.45D,DG,342.1,0.67) 3153800200036 ((27.)48-CD-115-G,2.23D,DG,527.9,0.275) 3153800200037 ((28.)48-CD-117-G,2.49HR,DG,273.4,0.28) 3153800200038 ((29.)48-CD-117-M,3.36HR,DG,1066.0,0.231) 3153800200039 ((30.)50-SN-128-G,59.1MIN,DG,482.3,0.59) 3153800200040 ((31.)51-SB-127,3.85D,DG,685.7,0.353) 3153800200041 ((32.)51-SB-129-G,4.32HR,DG,812.4,0.43) 3153800200042 ((33.)51-SB-131,23.03MIN,DG,943.0,0.44) 3153800200043 ((38.)52-TE-134,41.8MIN,DG,566.0,0.184) 3153800200044 ((39.)53-I-131,8.04D,DG,364.5,0.812) 3153800200045 ((40.)53-I-133-G,20.8HR,DG,529.9,0.87) 3153800200046 ((42.)53-I-135,6.55HR,DG,1260.4,0.286) 3153800200047 ((43.)53-I-135,6.55HR,DG,1131.5,0.225) 3153800200048 ((44.)54-XE-137,3.818MIN,DG,455.5,0.312) 3153800200049 ((45.)54-XE-138,14.08MIN,DG,434.5,0.203) 3153800200050 ((46.)55-CS-138-G,32.2MIN,DG,1435.8,0.763) 3153800200051 ((47.)55-CS-138-G,32.2MIN,DG,1009.8,0.298) 3153800200052 ((49.)56-BA-139,1.41HR,DG,165.9,0.22) 3153800200053 ((50.)56-BA-140,12.75D,DG,537.3,0.244) 3153800200054 ((51.)56-BA-141,18.27MIN,DG,190.3,0.463) 3153800200055 ((52.)56-BA-142,10.6MIN,DG,255.2,0.206) 3153800200056 ((53.)57-LA-142,1.542HR,DG,641.3,0.47) 3153800200057 ((54.)58-CE-141,32.5D,DG,145.4,0.484) 3153800200058 ((55.)58-CE-143,1.375D,DG,293.3,0.42) 3153800200059 ((56.)58-CE-144,284.4D,DG,133.5,0.111) 3153800200060 ((58.)58-CE-146,13.52MIN,DG,316.7,0.51) 3153800200061 ((59.)60-ND-147,10.98D,DG,531.0,0.13) 3153800200062 ((60.)61-PM-149,15.08HR,DG,286.0,0.0285) 3153800200063 T1/2(149Pm)=53 hr according to ENSDF 3153800200064 ((61.)61-PM-151,28.4HR,DG,340.0,0.22) 3153800200065 ((62.)62-SM-153,46.7HR,DG,103.2,0.283) 3153800200066 ERR-ANALYS (DATA-ERR) The statistical fluctuations of the mean 3153800200067 value from two to four determinations except in those 3153800200068 few cases where only single measurements could be done.3153800200069 STATUS (TABLE) Table II of Nucl.Sci.Eng 135(2000)227 3153800200070 HISTORY (20210923U) VS. SF8:FIS->EPI; STATUS and DECAY-DATA 3153800200071 moved from 001 3153800200072 ENDBIB 70 0 3153800200073 NOCOMMON 0 0 3153800200074 DATA 6 51 3153800200075 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 3153800200076 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3153800200077 35. 83. 0.187 1. 3153800200078 36. 85. 1. 0.635 0.206 2. 3153800200079 36. 87. 1.206 0.121 3. 3153800200080 36. 88. 2.098 0.083 4. 3153800200081 37. 89. 3.052 0.385 5. 3153800200082 37. 89. 2.888 0.093 6. 3153800200083 38. 91. 4.335 0.135 7. 3153800200084 38. 92. 4.410 0.130 8. 3153800200085 38. 93. 4.560 0.091 9. 3153800200086 39. 93. 5.134 0.348 11. 3153800200087 39. 94. 4.340 0.257 12. 3153800200088 39. 95. 5.032 0.061 13. 3153800200089 40. 95. 4.701 0.214 14. 3153800200090 40. 97. 6.408 0.147 15. 3153800200091 42. 99. 6.282 0.269 16. 3153800200092 42. 99. 7.365 0.590 17. 3153800200093 42. 101. 4.799 0.276 18. 3153800200094 43. 104. 5.237 0.211 19. 3153800200095 44. 103. 6.124 0.282 21. 3153800200096 44. 105. 5.014 0.314 22. 3153800200097 45. 107. 0.993 0.183 25. 3153800200098 47. 111. 0.083 0.014 26. 3153800200099 48. 115. 0. 0.055 0.004 27. 3153800200100 48. 117. 0. 0.038 0.006 28. 3153800200101 48. 117. 1. 0.007 0.002 29. 3153800200102 50. 128. 0.278 0.002 30. 3153800200103 51. 127. 0.135 0.015 31. 3153800200104 51. 129. 0.985 0.130 32. 3153800200105 51. 131. 3.089 0.175 33. 3153800200106 52. 134. 8.406 0.115 38. 3153800200107 53. 131. 3.313 0.110 39. 3153800200108 53. 133. 6.755 0.216 40. 3153800200109 53. 135. 8.422 0.118 42. 3153800200110 53. 135. 7.649 0.280 43. 3153800200111 54. 137. 8.650 0.027 44. 3153800200112 54. 138. 8.924 0.721 45. 3153800200113 55. 138. 11.669 0.246 46. 3153800200114 55. 138. 11.538 0.789 47. 3153800200115 56. 139. 7.245 0.105 49. 3153800200116 56. 140. 5.646 0.154 50. 3153800200117 56. 141. 5.448 0.048 51. 3153800200118 56. 142. 3.899 0.179 52. 3153800200119 57. 142. 6.057 0.159 53. 3153800200120 58. 141. 5.107 0.619 54. 3153800200121 58. 143. 4.952 0.122 55. 3153800200122 58. 144. 4.568 0.464 56. 3153800200123 58. 146. 3.572 0.225 58. 3153800200124 60. 147. 2.555 0.185 59. 3153800200125 61. 149. 1.679 60. 3153800200126 61. 151. 0.723 0.018 61. 3153800200127 62. 153. 0.332 62. 3153800200128 ENDDATA 53 0 3153800200129 ENDSUBENT 128 0 3153800299999 SUBENT 31538003 20211006 32023153800300001 BIB 8 46 3153800300002 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY,,EPI) 3153800300003 INC-SPECT Epi-cadmium spectrum 3153800300004 FACILITY (REAC,3INDTRM) The target assemblies were irradiated 3153800300005 30 min to 7 hr in a fixed water-moderated, highly 3153800300006 enriched uranium-fueled swimming pool reactor APSARA 3153800300007 at a flux of 10**11 n/cm2/s. 3153800300008 SAMPLE About 200 mu-g of isotopically pure 237Np in the 3153800300009 nitrate form was dried in an aluminum foil of the 3153800300010 same thickness and folded into a small packet. 3153800300011 DECAY-DATA ((8.)38-SR-92,2.71HR,DG,1384.1,0.90) 3153800300012 ((14.)40-ZR-95,64.02D,DG,756.7,0.545) 3153800300013 ((15.)40-ZR-97,16.9HR,DG,743.3,0.928) 3153800300014 ((16.)42-MO-99,2.748D,DG,140.5,0.907) 3153800300015 ((21.)44-RU-103,39.254D,DG,497.1,0.887) 3153800300016 ((22.)44-RU-105,4.44HR,DG,724.3,0.467) 3153800300017 ((26.)47-AG-111-G,7.45D,DG,342.1,0.67) 3153800300018 ((27.)48-CD-115-G,2.23D,DG,527.9,0.275) 3153800300019 ((28.)48-CD-117-G,2.49HR,DG,273.4,0.28) 3153800300020 ((30.)50-SN-128-G,59.1MIN,DG,482.3,0.59) 3153800300021 ((31.)51-SB-127,3.85D,DG,685.7,0.353) 3153800300022 ((32.)51-SB-129-G,4.32HR,DG,812.4,0.43) 3153800300023 ((37.)52-TE-132,3.26D,DG,228.3,0.882) 3153800300024 ((38.)52-TE-134,41.8MIN,DG,566.0,0.184) 3153800300025 ((39.)53-I-131,8.04D,DG,364.5,0.812) 3153800300026 ((40.)53-I-133-G,20.8HR,DG,529.9,0.87) 3153800300027 ((42.)53-I-135,6.55HR,DG,1260.4,0.286) 3153800300028 ((44.)54-XE-137,3.818MIN,DG,455.5,0.312) 3153800300029 ((46.)55-CS-138-G,32.2MIN,DG,1435.8,0.763) 3153800300030 ((49.)56-BA-139,1.41HR,DG,165.9,0.22) 3153800300031 ((50.)56-BA-140,12.75D,DG,537.3,0.244) 3153800300032 ((53.)57-LA-142,1.542HR,DG,641.3,0.47) 3153800300033 ((54.)58-CE-141,32.5D,DG,145.4,0.484) 3153800300034 ((55.)58-CE-143,1.375D,DG,293.3,0.42) 3153800300035 ((56.)58-CE-144,284.4D,DG,133.5,0.111) 3153800300036 ((59.)60-ND-147,10.98D,DG,531.0,0.13) 3153800300037 ((60.)61-PM-149,15.08HR,DG,286.0,0.0285) 3153800300038 T1/2(149Pm)=53 hr according to ENSDF 3153800300039 ((61.)61-PM-151,28.4HR,DG,340.0,0.22) 3153800300040 ((63.)59-PR-146,24.15MIN,DG,453.9,0.48) 3153800300041 ((64.)38-SR-91,9.52HR,DG,749.7,0.236) 3153800300042 ERR-ANALYS (DATA-ERR) The statistical fluctuations of the mean 3153800300043 value from two to four determinations except in those 3153800300044 few cases where only single measurements could be done.3153800300045 STATUS (TABLE) Table III of Nucl.Sci.Eng 135(2000)227 3153800300046 HISTORY (20210923A) VS. SF8:FIS->EPI; STATUS and DECAY-DATA 3153800300047 moved from 001 3153800300048 ENDBIB 46 0 3153800300049 NOCOMMON 0 0 3153800300050 DATA 6 29 3153800300051 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 3153800300052 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3153800300053 38. 91. 3.655 0.190 64. 3153800300054 38. 92. 5.155 0.345 8. 3153800300055 40. 95. 4.872 0.293 14. 3153800300056 40. 97. 6.925 0.055 15. 3153800300057 42. 99. 5.145 0.495 16. 3153800300058 44. 103. 5.195 0.165 21. 3153800300059 44. 105. 3.539 0.117 22. 3153800300060 47. 111. 0.106 26. 3153800300061 48. 115. 0. 0.048 0.002 27. 3153800300062 48. 117. 0. 0.033 0.008 28. 3153800300063 50. 128. 0.811 0.081 30. 3153800300064 51. 127. 0.474 0.045 31. 3153800300065 51. 129. 1.919 0.011 32. 3153800300066 52. 132. 4.928 0.020 37. 3153800300067 52. 134. 3.992 0.065 38. 3153800300068 53. 131. 3.408 0.036 39. 3153800300069 53. 133. 4.318 0.179 40. 3153800300070 53. 135. 6.045 0.325 42. 3153800300071 55. 138. 5.405 0.385 46. 3153800300072 56. 139. 5.900 0.030 49. 3153800300073 56. 140. 5.640 0.698 50. 3153800300074 57. 142. 5.525 0.285 53. 3153800300075 58. 141. 5.711 0.026 54. 3153800300076 58. 143. 4.785 0.065 55. 3153800300077 58. 144. 4.131 0.063 56. 3153800300078 60. 147. 1.990 0.080 59. 3153800300079 61. 149. 1.138 0.217 60. 3153800300080 61. 151. 0.666 0.063 61. 3153800300081 62. 153. 0.273 63. 3153800300082 ENDDATA 31 0 3153800300083 ENDSUBENT 82 0 3153800399999 SUBENT 31538004 20211006 32023153800400001 BIB 8 34 3153800400002 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY,,EPI) 3153800400003 INC-SPECT Epi-cadmium spectrum 3153800400004 FACILITY (REAC,3INDTRM)) For short-lived fission products the 3153800400005 237Np facility of the heavy water-moderated natural 3153800400006 uranium-fueled CIRUS reactor at a flux of 3153800400007 2 x 10**12 n/cm2/s. 3153800400008 SAMPLE About 200 mu-g of isotopically pure 237Np in the 3153800400009 nitrate form was dried in an aluminum foil of the 3153800400010 same thickness and folded into a small packet. 3153800400011 DECAY-DATA ((7.)38-SR-91,9.52HR,DG,1024.3,0.334) 3153800400012 ((9.)38-SR-93,7.42MIN,DG,875.9,0.239) 3153800400013 ((10.)38-SR-94,1.235MIN,DG,1427.7,0.942) 3153800400014 ((13.)39-Y-95,10.3MIN,DG,954.1,0.134) 3153800400015 ((19.)43-TC-104,18.3MIN,DG,358.0,0.89) 3153800400016 ((20.)43-TC-105,7.7MIN,DG,143.2,0.107) 3153800400017 ((23.)44-RU-108,4.55MIN,DG,164.9,0.28) 3153800400018 ((33.)51-SB-131,23.03MIN,DG,943.0,0.44) 3153800400019 ((34.)51-SB-132-M,2.8MIN,DG,696.6,0.01) 3153800400020 ((35.)51-SB-132-G,4.15MIN,DG,696.6,0.86) 3153800400021 ((36.)51-SB-133,2.36MIN,DG,1096.2,0.305) 3153800400022 ((44.)54-XE-137,3.818MIN,DG,455.5,0.312) 3153800400023 ((45.)54-XE-138,14.08MIN,DG,434.5,0.203) 3153800400024 ((48.)55-CS-140,1.062MIN,DG,602.4,0.7) 3153800400025 ((49.)56-BA-139,1.41HR,DG,165.9,0.22) 3153800400026 ((51.)56-BA-141,18.27MIN,DG,190.3,0.463) 3153800400027 ((52.)56-BA-142,10.6MIN,DG,255.2,0.206) 3153800400028 ((57.)58-CE-145,2.98MIN,DG,723.9,0.639) 3153800400029 ((58.)58-CE-146,13.52MIN,DG,316.7,0.51) 3153800400030 ERR-ANALYS (DATA-ERR) The statistical fluctuations of the mean 3153800400031 value from two to four determinations except in those 3153800400032 few cases where only single measurements could be done.3153800400033 STATUS (TABLE) Table III of Nucl.Sci.Eng 135(2000)227 3153800400034 HISTORY (20210923A) VS. SF8:FIS->EPI; STATUS and DECAY-DATA 3153800400035 moved from 001. 3153800400036 ENDBIB 34 0 3153800400037 NOCOMMON 0 0 3153800400038 DATA 6 18 3153800400039 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 3153800400040 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3153800400041 37. 89. 2.212 0.137 7. 3153800400042 38. 93. 4.362 0.007 9. 3153800400043 38. 94. 4.195 0.015 10. 3153800400044 39. 95. 6.150 0.233 13. 3153800400045 43. 104. 5.375 0.135 19. 3153800400046 43. 105. 5.451 0.493 20. 3153800400047 44. 108. 1.096 0.211 23. 3153800400048 51. 131. 2.155 0.091 33. 3153800400049 51. 132. 0. 0.745 0.091 35. 3153800400050 51. 132. 1. 1.418 0.387 34. 3153800400051 51. 133. 1.577 0.320 36. 3153800400052 54. 137. 5.391 0.040 44. 3153800400053 54. 138. 4.499 0.417 45. 3153800400054 55. 140. 3.875 0.055 48. 3153800400055 56. 141. 6.565 0.605 51. 3153800400056 56. 142. 3.172 0.187 52. 3153800400057 58. 145. 3.355 0.195 57. 3153800400058 58. 146. 2.267 0.036 58. 3153800400059 ENDDATA 20 0 3153800400060 ENDSUBENT 59 0 3153800499999 SUBENT 31538005 20211006 32023153800500001 BIB 8 45 3153800500002 REACTION (94-PU-238(N,F)ELEM/MASS,CUM,FY,,EPI) 3153800500003 INC-SPECT Epi-cadmium spectrum 3153800500004 FACILITY (REAC,3INDTRM) The target assemblies were irradiated 3153800500005 for 30 min to 7 hr in a fixed water-moderated, highly 3153800500006 enriched uranium-fueled swimming pool reactor APSARA 3153800500007 at a flux of 10**11 n/cm2/s. 3153800500008 SAMPLE The target of 238Pu (20 mu-g) was prepared by 3153800500009 electrodeposition from an isopropyl alcohol medium on 3153800500010 thin platinum planchets. Composition of 240Pu was: 3153800500011 240Pu - 99.48%, 239Pu - 0.39%, 241Pu - 0.13%, 3153800500012 242Pu - 0.003% 3153800500013 DECAY-DATA ((7.)38-SR-91,9.52HR,DG,1024.3,0.334) 3153800500014 ((8.)38-SR-92,2.71HR,DG,1384.1,0.90) 3153800500015 ((11.)39-Y-93-G,10.25HR,DG,266.9,0.068) 3153800500016 ((12.)39-Y-94,18.7MIN,DG,918.7,0.56) 3153800500017 ((14.)40-ZR-95,64.02D,DG,756.7,0.545) 3153800500018 ((15.)40-ZR-97,16.9HR,DG,743.3,0.928) 3153800500019 ((16.)42-MO-99,2.748D,DG,140.5,0.907) 3153800500020 ((19.)43-TC-104,18.3MIN,DG,358.0,0.89) 3153800500021 ((21.)44-RU-103,39.254D,DG,497.1,0.887) 3153800500022 ((22.)44-RU-105,4.44HR,DG,724.3,0.467) 3153800500023 ((25.)45-RH-107,21.7MIN,DG,302.8,0.66) 3153800500024 ((30.)50-SN-128-G,59.1MIN,DG,482.3,0.59) 3153800500025 ((32.)51-SB-129-G,4.32HR,DG,812.4,0.43) 3153800500026 ((33.)51-SB-131,23.03MIN,DG,943.0,0.44) 3153800500027 ((37.)52-TE-132,3.26D,DG,228.3,0.882) 3153800500028 ((38.)52-TE-134,41.8MIN,DG,566.0,0.184) 3153800500029 ((39.)53-I-131,8.04D,DG,364.5,0.812) 3153800500030 ((40.)53-I-133-G,20.8HR,DG,529.9,0.87) 3153800500031 ((41.)53-I-134-G,82.6MIN,DG,847.0,0.954) 3153800500032 T1/2(134gI)=52.5 min according to ENSD 3153800500033 ((42.)53-I-135,6.55HR,DG,1260.4,0.286) 3153800500034 ((46.)55-CS-138-G,32.2MIN,DG,1435.8,0.763) 3153800500035 ((49.)56-BA-139,1.41HR,DG,165.9,0.22) 3153800500036 ((50.)56-BA-140,12.75D,DG,537.3,0.244) 3153800500037 ((53.)57-LA-142,1.542HR,DG,641.3,0.47) 3153800500038 ((54.)58-CE-141,32.5D,DG,145.4,0.484) 3153800500039 ((55.)58-CE-143,1.375D,DG,293.3,0.42) 3153800500040 ((59.)60-ND-147,10.98D,DG,531.0,0.13) 3153800500041 ERR-ANALYS (DATA-ERR) The statistical fluctuations of the mean 3153800500042 value from two to four determinations except in those 3153800500043 few cases where only single measurements could be done.3153800500044 STATUS (TABLE) Table IV of Nucl.Sci.Eng 135(2000)227 3153800500045 HISTORY (20210923A) VS. SF8:FIS->EPI; STATUS and DECAY-DATA 3153800500046 moved from 001. 3153800500047 ENDBIB 45 0 3153800500048 NOCOMMON 0 0 3153800500049 DATA 5 27 3153800500050 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 3153800500051 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3153800500052 38. 91. 3.816 0.006 7. 3153800500053 38. 92. 4.288 0.373 8. 3153800500054 39. 93. 5.201 0.439 11. 3153800500055 39. 94. 5.921 0.311 12. 3153800500056 40. 95. 9.171 14. 3153800500057 40. 97. 8.493 0.291 15. 3153800500058 42. 99. 8.240 0.353 16. 3153800500059 43. 104. 8.142 0.587 19. 3153800500060 44. 103. 10.212 0.148 21. 3153800500061 44. 105. 8.162 0.174 22. 3153800500062 45. 107. 5.202 25. 3153800500063 50. 128. 1.218 0.201 30. 3153800500064 51. 129. 2.135 0.212 32. 3153800500065 51. 131. 2.876 0.521 33. 3153800500066 52. 132. 8.195 0.066 37. 3153800500067 52. 134. 6.262 0.582 38. 3153800500068 53. 131. 5.717 39. 3153800500069 53. 133. 9.049 40. 3153800500070 53. 134. 8.233 41. 3153800500071 53. 135. 7.909 0.200 42. 3153800500072 55. 138. 6.041 0.108 46. 3153800500073 56. 139. 9.447 0.159 49. 3153800500074 56. 140. 9.875 0.815 50. 3153800500075 57. 142. 6.809 0.029 53. 3153800500076 58. 141. 6.416 0.220 54. 3153800500077 58. 143. 5.608 0.154 55. 3153800500078 60. 147. 4.310 0.090 59. 3153800500079 ENDDATA 29 0 3153800500080 ENDSUBENT 79 0 3153800599999 SUBENT 31538006 20211006 32023153800600001 BIB 8 47 3153800600002 REACTION (94-PU-240(N,F)ELEM/MASS,CUM,FY,,EPI) 3153800600003 INC-SPECT Epi-cadmium spectrum 3153800600004 FACILITY (REAC,3INDTRM)) The target assemblies were irradiated 3153800600005 for 30 min to 7 hr in a fixed water-moderated, highly 3153800600006 enriched uranium-fueled swimming pool reactor APSARA 3153800600007 at a flux of 10**11 n/cm2/s. 3153800600008 SAMPLE The target of 240Pu (96 mu-g) was prepared by 3153800600009 electrodeposition from an isopropyl alcohol medium on 3153800600010 thin platinum planchets. Composition of 240Pu was: 3153800600011 240Pu - 99.48%, 239Pu - 0.39%, 241Pu - 0.13%, 3153800600012 242Pu - 0.003% 3153800600013 DECAY-DATA ((6.)37-RB-89,15.2MIN,DG,1248.1,0.426) 3153800600014 ((7.)38-SR-91,9.52HR,DG,1024.3,0.334) 3153800600015 ((8.)38-SR-92,2.71HR,DG,1384.1,0.90) 3153800600016 ((11.)39-Y-93-G,10.25HR,DG,266.9,0.068) 3153800600017 ((12.)39-Y-94,18.7MIN,DG,918.7,0.56) 3153800600018 ((13.)39-Y-95,10.3MIN,DG,954.1,0.134) 3153800600019 ((15.)40-ZR-97,16.9HR,DG,743.3,0.928) 3153800600020 ((16.)42-MO-99,2.748D,DG,140.5,0.907) 3153800600021 ((18.)42-MO-101,14.6MIN,DG,590.9,0.164) 3153800600022 ((19.)43-TC-104,18.3MIN,DG,358.0,0.89) 3153800600023 ((21.)44-RU-103,39.254D,DG,497.1,0.887) 3153800600024 ((22.)44-RU-105,4.44HR,DG,724.3,0.467) 3153800600025 ((25.)45-RH-107,21.7MIN,DG,302.8,0.66) 3153800600026 ((30.)50-SN-128-G,59.1MIN,DG,482.3,0.59) 3153800600027 ((32.)51-SB-129-G,4.32HR,DG,812.4,0.43) 3153800600028 ((33.)51-SB-131,23.03MIN,DG,943.0,0.44) 3153800600029 ((37.)52-TE-132,3.26D,DG,228.3,0.882) 3153800600030 ((38.)52-TE-134,41.8MIN,DG,566.0,0.184) 3153800600031 ((39.)53-I-131,8.04D,DG,364.5,0.812) 3153800600032 ((40.)53-I-133-G,20.8HR,DG,529.9,0.87) 3153800600033 ((42.)53-I-135,6.55HR,DG,1260.4,0.286) 3153800600034 ((46.)55-CS-138-G,32.2MIN,DG,1435.8,0.763) 3153800600035 ((49.)56-BA-139,1.41HR,DG,165.9,0.22) 3153800600036 ((50.)56-BA-140,12.75D,DG,537.3,0.244) 3153800600037 ((51.)56-BA-141,18.27MIN,DG,190.3,0.463) 3153800600038 ((52.)56-BA-142,10.6MIN,DG,255.2,0.206) 3153800600039 ((53.)57-LA-142,1.542HR,DG,641.3,0.47) 3153800600040 ((54.)58-CE-141,32.5D,DG,145.4,0.484) 3153800600041 ((55.)58-CE-143,1.375D,DG,293.3,0.42) 3153800600042 ((58.)58-CE-146,13.52MIN,DG,316.7,0.51) 3153800600043 ERR-ANALYS (DATA-ERR) The statistical fluctuations of the mean 3153800600044 value from two to four determinations except in those 3153800600045 few cases where only single measurements could be done.3153800600046 STATUS (TABLE) Table V of Nucl.Sci.Eng 135(2000)227 3153800600047 HISTORY (20210923A) VS. SF8:FIS->EPI; STATUS and DECAY-DATA 3153800600048 moved from 001. 3153800600049 ENDBIB 47 0 3153800600050 NOCOMMON 0 0 3153800600051 DATA 5 30 3153800600052 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 3153800600053 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3153800600054 37. 89. 1.409 6. 3153800600055 38. 91. 2.038 0.066 7. 3153800600056 38. 92. 2.403 0.024 8. 3153800600057 39. 93. 3.127 0.124 11. 3153800600058 39. 94. 2.707 0.071 12. 3153800600059 39. 95. 4.542 13. 3153800600060 40. 97. 4.725 0.031 15. 3153800600061 42. 99. 5.460 0.110 16. 3153800600062 42. 101. 3.902 18. 3153800600063 43. 104. 4.107 0.542 19. 3153800600064 44. 103. 6.081 0.153 21. 3153800600065 44. 105. 6.008 0.117 22. 3153800600066 45. 107. 3.459 0.196 25. 3153800600067 50. 128. 0.431 0.035 30. 3153800600068 51. 129. 1.049 0.041 32. 3153800600069 51. 131. 1.682 0.286 33. 3153800600070 52. 132. 4.721 0.020 37. 3153800600071 52. 134. 4.988 0.157 38. 3153800600072 53. 131. 2.982 0.119 39. 3153800600073 53. 133. 5.387 0.014 40. 3153800600074 53. 135. 5.631 0.335 42. 3153800600075 55. 138. 5.561 0.762 46. 3153800600076 56. 139. 5.569 0.157 49. 3153800600077 56. 140. 4.545 0.254 50. 3153800600078 56. 141. 5.046 0.225 51. 3153800600079 56. 142. 3.161 52. 3153800600080 57. 142. 4.060 0.298 53. 3153800600081 58. 141. 7.442 0.111 54. 3153800600082 58. 143. 3.607 0.057 55. 3153800600083 58. 146. 1.566 0.172 58. 3153800600084 ENDDATA 32 0 3153800600085 ENDSUBENT 84 0 3153800699999 SUBENT 31538007 20211006 32023153800700001 BIB 8 46 3153800700002 REACTION (95-AM-243(N,F)ELEM/MASS,CUM,FY,,EPI) 3153800700003 INC-SPECT Epi-cadmium spectrum 3153800700004 FACILITY (REAC,3INDTRM)) The target assemblies were irradiated 3153800700005 30 min to 7 hr in a fixed water-moderated, highly 3153800700006 enriched uranium-fueled swimming pool reactor APSARA 3153800700007 at a flux of 10**11 n/cm2/s. 3153800700008 SAMPLE The target of 243Am (90 mu-g) was prepared by 3153800700009 electrodeposition from an isopropyl alcohol medium on 3153800700010 thin platinum planchets. Composition of 243Am was: 3153800700011 243Am - 99.998%, 241Am - 0.0016%, 242mAm - 0.00021% 3153800700012 DECAY-DATA ((5.)37-RB-89,15.2MIN,DG,1032.1,0.58) 3153800700013 ((7.)38-SR-91,9.52HR,DG,1024.3,0.334) 3153800700014 ((8.)38-SR-92,2.71HR,DG,1384.1,0.90) 3153800700015 ((11.)39-Y-93-G,10.25HR,DG,266.9,0.068) 3153800700016 ((12.)39-Y-94,18.7MIN,DG,918.7,0.56) 3153800700017 ((13.)39-Y-95,10.3MIN,DG,954.1,0.134) 3153800700018 ((14.)40-ZR-95,64.02D,DG,756.7,0.545) 3153800700019 ((15.)40-ZR-97,16.9HR,DG,743.3,0.928) 3153800700020 ((16.)42-MO-99,2.748D,DG,140.5,0.907) 3153800700021 ((18.)42-MO-101,14.6MIN,DG,590.9,0.164) 3153800700022 ((19.)43-TC-104,18.3MIN,DG,358.0,0.89) 3153800700023 ((21.)44-RU-103,39.254D,DG,497.1,0.887) 3153800700024 ((22.)44-RU-105,4.44HR,DG,724.3,0.467) 3153800700025 ((24.)45-RH-105-G,35.36HR,DG,318.9,0.19) 3153800700026 ((25.)45-RH-107,21.7MIN,DG,302.8,0.66) 3153800700027 ((30.)50-SN-128-G,59.1MIN,DG,482.3,0.59) 3153800700028 ((32.)51-SB-129-G,4.32HR,DG,812.4,0.43) 3153800700029 ((33.)51-SB-131,23.03MIN,DG,943.0,0.44) 3153800700030 ((38.)52-TE-134,41.8MIN,DG,566.0,0.184) 3153800700031 ((39.)53-I-131,8.04D,DG,364.5,0.812) 3153800700032 ((40.)53-I-133-G,20.8HR,DG,529.9,0.87) 3153800700033 ((42.)53-I-135,6.55HR,DG,1260.4,0.286) 3153800700034 ((46.)55-CS-138-G,32.2MIN,DG,1435.8,0.763) 3153800700035 ((49.)56-BA-139,1.41HR,DG,165.9,0.22) 3153800700036 ((50.)56-BA-140,12.75D,DG,537.3,0.244) 3153800700037 ((51.)56-BA-141,18.27MIN,DG,190.3,0.463) 3153800700038 ((53.)57-LA-142,1.542HR,DG,641.3,0.47) 3153800700039 ((54.)58-CE-141,32.5D,DG,145.4,0.484) 3153800700040 ((55.)58-CE-143,1.375D,DG,293.3,0.42) 3153800700041 ((63.)59-PR-146,24.15MIN,DG,453.9,0.48) 3153800700042 ERR-ANALYS (DATA-ERR) The statistical fluctuations of the mean 3153800700043 value from two to four determinations except in those 3153800700044 few cases where only single measurements could be done.3153800700045 STATUS (TABLE) Table VI of Nucl.Sci.Eng 135(2000)227 3153800700046 HISTORY (20210923A) VS. SF8:FIS->EPI; STATUS and DECAY-DATA 3153800700047 moved from 001. 3153800700048 ENDBIB 46 0 3153800700049 NOCOMMON 0 0 3153800700050 DATA 5 30 3153800700051 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 3153800700052 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3153800700053 37. 89. 1.099 5. 3153800700054 38. 91. 1.480 7. 3153800700055 38. 92. 1.935 0.095 8. 3153800700056 39. 93. 2.247 11. 3153800700057 39. 94. 2.232 0.162 12. 3153800700058 39. 95. 4.173 13. 3153800700059 40. 95. 4.550 14. 3153800700060 40. 97. 3.870 0.370 15. 3153800700061 42. 99. 5.495 0.035 16. 3153800700062 42. 101. 6.869 0.561 18. 3153800700063 43. 104. 6.067 0.477 19. 3153800700064 44. 103. 6.510 21. 3153800700065 44. 105. 6.255 0.165 22. 3153800700066 45. 105. 6.510 24. 3153800700067 45. 107. 6.710 25. 3153800700068 50. 128. 0.740 30. 3153800700069 51. 129. 1.429 32. 3153800700070 51. 131. 1.960 0.216 33. 3153800700071 52. 134. 4.620 0.312 38. 3153800700072 53. 131. 3.290 0.210 39. 3153800700073 53. 133. 5.360 40. 3153800700074 53. 135. 6.289 0.571 42. 3153800700075 55. 138. 6.114 0.708 46. 3153800700076 56. 139. 7.355 0.155 49. 3153800700077 56. 140. 6.640 50. 3153800700078 56. 141. 7.400 51. 3153800700079 57. 142. 4.563 0.791 53. 3153800700080 58. 141. 4.850 54. 3153800700081 58. 143. 4.740 0.140 55. 3153800700082 59. 146. 3.855 0.824 63. 3153800700083 ENDDATA 32 0 3153800700084 ENDSUBENT 83 0 3153800799999 SUBENT 31538008 20211006 32023153800800001 BIB 8 52 3153800800002 REACTION (96-CM-244(N,F)ELEM/MASS,CUM,FY,,EPI) 3153800800003 INC-SPECT Epi-cadmium spectrum 3153800800004 FACILITY (REAC,3INDTRM) The target assemblies were irradiated 3153800800005 for 30 min to 7 hr in a fixed water-moderated, highly 3153800800006 enriched uranium-fueled swimming pool reactor APSARA 3153800800007 at a flux of 10**11 n/cm2/s. 3153800800008 SAMPLE The target of 244Cm (96 mu-g) was prepared by 3153800800009 electrodeposition from an isopropyl alcohol medium on 3153800800010 thin platinum planchets. Composition of 244Cm was: 3153800800011 244Cm - 99.43%, 245Cm - 0.065%, 246Cm - 0.48%, 3153800800012 247Cm - 0.006%, 248Cm - 0.015% 3153800800013 DECAY-DATA ((7.)38-SR-91,9.52HR,DG,1024.3,0.334) 3153800800014 ((8.)38-SR-92,2.71HR,DG,1384.1,0.90) 3153800800015 ((11.)39-Y-93-G,10.25HR,DG,266.9,0.068) 3153800800016 ((12.)39-Y-94,18.7MIN,DG,918.7,0.56) 3153800800017 ((13.)39-Y-95,10.3MIN,DG,954.1,0.134) 3153800800018 ((15.)40-ZR-97,16.9HR,DG,743.3,0.928) 3153800800019 ((16.)42-MO-99,2.748D,DG,140.5,0.907) 3153800800020 ((18.)42-MO-101,14.6MIN,DG,590.9,0.164) 3153800800021 ((19.)43-TC-104,18.3MIN,DG,358.0,0.89) 3153800800022 ((21.)44-RU-103,39.254D,DG,497.1,0.887) 3153800800023 ((22.)44-RU-105,4.44HR,DG,724.3,0.467) 3153800800024 ((24.)45-RH-105-G,35.36HR,DG,318.9,0.19) 3153800800025 ((25.)45-RH-107,21.7MIN,DG,302.8,0.66) 3153800800026 ((30.)50-SN-128-G,59.1MIN,DG,482.3,0.59) 3153800800027 ((32.)51-SB-129-G,4.32HR,DG,812.4,0.43) 3153800800028 ((33.)51-SB-131,23.03MIN,DG,943.0,0.44) 3153800800029 ((37.)52-TE-132,3.26D,DG,228.3,0.882) 3153800800030 ((38.)52-TE-134,41.8MIN,DG,566.0,0.184) 3153800800031 ((39.)53-I-131,8.04D,DG,364.5,0.812) 3153800800032 ((40.)53-I-133-G,20.8HR,DG,529.9,0.87) 3153800800033 ((41.)53-I-134-G,82.6MIN,DG,847.0,0.954) 3153800800034 T1/2(134gI)=52.5 min according to ENSD 3153800800035 ((42.)53-I-135,6.55HR,DG,1260.4,0.286) 3153800800036 ((46.)55-CS-138-G,32.2MIN,DG,1435.8,0.763) 3153800800037 ((49.)56-BA-139,1.41HR,DG,165.9,0.22) 3153800800038 ((50.)56-BA-140,12.75D,DG,537.3,0.244) 3153800800039 ((51.)56-BA-141,18.27MIN,DG,190.3,0.463) 3153800800040 ((52.)56-BA-142,10.6MIN,DG,255.2,0.206) 3153800800041 ((53.)57-LA-142,1.542HR,DG,641.3,0.47) 3153800800042 ((54.)58-CE-141,32.5D,DG,145.4,0.484) 3153800800043 ((55.)58-CE-143,1.375D,DG,293.3,0.42) 3153800800044 ((58.)58-CE-146,13.52MIN,DG,316.7,0.51) 3153800800045 ((59.)60-ND-147,10.98D,DG,531.0,0.13) 3153800800046 ((64.)38-SR-91,9.52HR,DG,749.7,0.236) 3153800800047 ((65.)44-RU-105,4.44HR,DG,469.4,0.173) 3153800800048 ERR-ANALYS (DATA-ERR) The statistical fluctuations of the mean 3153800800049 value from two to four determinations except in those 3153800800050 few cases where only single measurements could be done.3153800800051 STATUS (TABLE) Table VII of Nucl.Sci.Eng 135(2000)227 3153800800052 HISTORY (20210923A) VS. SF8:FIS->EPI; STATUS and DECAY-DATA 3153800800053 moved from 001. 3153800800054 ENDBIB 52 0 3153800800055 NOCOMMON 0 0 3153800800056 DATA 5 34 3153800800057 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 3153800800058 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3153800800059 38. 91. 0.690 64. 3153800800060 38. 91. 1.210 0.270 7. 3153800800061 38. 92. 1.495 0.145 8. 3153800800062 39. 93. 1.899 11. 3153800800063 39. 94. 1.460 0.021 12. 3153800800064 39. 95. 4.500 13. 3153800800065 40. 97. 3.432 0.482 15. 3153800800066 42. 99. 4.508 0.298 16. 3153800800067 42. 101. 5.951 0.901 18. 3153800800068 43. 104. 4.828 0.178 19. 3153800800069 44. 103. 6.818 0.858 21. 3153800800070 44. 105. 6.384 0.564 22. 3153800800071 44. 105. 5.570 65. 3153800800072 45. 105. 6.020 24. 3153800800073 45. 107. 5.611 0.371 25. 3153800800074 50. 128. 0.705 30. 3153800800075 51. 129. 1.199 32. 3153800800076 51. 131. 1.429 0.041 33. 3153800800077 52. 132. 4.054 0.194 37. 3153800800078 52. 134. 3.063 0.313 38. 3153800800079 53. 131. 2.946 0.216 39. 3153800800080 53. 133. 4.590 40. 3153800800081 53. 134. 4.543 41. 3153800800082 53. 135. 4.700 0.550 42. 3153800800083 55. 138. 4.288 0.128 46. 3153800800084 56. 139. 6.231 0.291 49. 3153800800085 56. 140. 4.926 0.406 50. 3153800800086 56. 141. 5.521 0.010 51. 3153800800087 56. 142. 3.240 52. 3153800800088 57. 142. 4.128 0.398 53. 3153800800089 58. 141. 3.820 0.020 54. 3153800800090 58. 143. 3.853 0.243 55. 3153800800091 58. 146. 1.868 0.138 58. 3153800800092 60. 147. 1.923 59. 3153800800093 ENDDATA 36 0 3153800800094 ENDSUBENT 93 0 3153800899999 SUBENT 31538009 20211005 32023153800900001 BIB 5 9 3153800900002 REACTION 1(92-U-238(N,F),,NU,,EPI,DERIV) 3153800900003 2(92-U-238(N,F),,AP,LF,EPI) 3153800900004 3(92-U-238(N,F),,AP,HF,EPI) 3153800900005 ANALYSIS The average emitted neutron number is 3153800900006 (nu = AF -AL - AH), where AF - compound nucleus mass; 3153800900007 AL - average light mass; AH - average heavy mass 3153800900008 ERR-ANALYS (DATA-ERR) No information on sources of uncertainty. 3153800900009 STATUS (TABLE) Table VIII of Nucl.Sci.Eng 135(2000)227 3153800900010 HISTORY (20210923A) VS. SF8:FIS->EPI STATUS moved from 001 3153800900011 ENDBIB 9 0 3153800900012 NOCOMMON 0 0 3153800900013 DATA 4 1 3153800900014 DATA 1DATA-ERR 1DATA 2DATA 3 3153800900015 PRT/FIS PRT/FIS NO-DIM NO-DIM 3153800900016 3.01 0.27 97.2 138.8 3153800900017 ENDDATA 3 0 3153800900018 ENDSUBENT 17 0 3153800999999 SUBENT 31538010 20211005 32023153801000001 BIB 5 9 3153801000002 REACTION 1(93-NP-237(N,F),,NU,,EPI,DERIV) 3153801000003 2(93-NP-237(N,F),,AP,LF,EPI) 3153801000004 3(93-NP-237(N,F),,AP,HF,EPI) 3153801000005 ANALYSIS The average emitted neutron number is 3153801000006 (nu = AF -AL - AH), where AF - compound nucleus mass; 3153801000007 AL - average light mass; AH - average heavy mass 3153801000008 ERR-ANALYS (DATA-ERR) No information on sources of uncertainty. 3153801000009 STATUS (TABLE) Table VIII of Nucl.Sci.Eng 135(2000)227 3153801000010 HISTORY (20210923A) VS. SF8:FIS->EPI STATUS moved from 001 3153801000011 ENDBIB 9 0 3153801000012 NOCOMMON 0 0 3153801000013 DATA 4 1 3153801000014 DATA 1DATA-ERR 1DATA 2DATA 3 3153801000015 PRT/FIS PRT/FIS NO-DIM NO-DIM 3153801000016 2.11 0.17 97.81 138.08 3153801000017 ENDDATA 3 0 3153801000018 ENDSUBENT 17 0 3153801099999 SUBENT 31538011 20211005 32023153801100001 BIB 5 9 3153801100002 REACTION 1(94-PU-238(N,F),,NU,,EPI,DERIV) 3153801100003 2(94-PU-238(N,F),,AP,LF,EPI) 3153801100004 3(94-PU-238(N,F),,AP,HF,EPI) 3153801100005 ANALYSIS The average emitted neutron number is 3153801100006 (nu = AF -AL - AH), where AF - compound nucleus mass; 3153801100007 AL - average light mass; AH - average heavy mass 3153801100008 ERR-ANALYS (DATA-ERR) No information on sources of uncertainty. 3153801100009 STATUS (TABLE) Table VIII of Nucl.Sci.Eng 135(2000)227 3153801100010 HISTORY (20210923A) VS. SF8:FIS->EPI STATUS moved from 001 3153801100011 ENDBIB 9 0 3153801100012 NOCOMMON 0 0 3153801100013 DATA 4 1 3153801100014 DATA 1DATA-ERR 1DATA 2DATA 3 3153801100015 PRT/FIS PRT/FIS NO-DIM NO-DIM 3153801100016 2.85 0.08 98.96 137.19 3153801100017 ENDDATA 3 0 3153801100018 ENDSUBENT 17 0 3153801199999 SUBENT 31538012 20211005 32023153801200001 BIB 5 9 3153801200002 REACTION 1(94-PU-240(N,F),,NU,,EPI,DERIV) 3153801200003 2(94-PU-240(N,F),,AP,LF,EPI) 3153801200004 3(94-PU-240(N,F),,AP,HF,EPI) 3153801200005 ANALYSIS The average emitted neutron number is 3153801200006 (nu = AF -AL - AH), where AF - compound nucleus mass; 3153801200007 AL - average light mass; AH - average heavy mass 3153801200008 ERR-ANALYS (DATA-ERR) No information on sources of uncertainty. 3153801200009 STATUS (TABLE) Table VIII of Nucl.Sci.Eng 135(2000)227 3153801200010 HISTORY (20210923A) VS. SF8:FIS->EPI STATUS moved from 001 3153801200011 ENDBIB 9 0 3153801200012 NOCOMMON 0 0 3153801200013 DATA 4 1 3153801200014 DATA 1DATA-ERR 1DATA 2DATA 3 3153801200015 PRT/FIS PRT/FIS NO-DIM NO-DIM 3153801200016 4.56 0.79 99.19 137.25 3153801200017 ENDDATA 3 0 3153801200018 ENDSUBENT 17 0 3153801299999 SUBENT 31538013 20211005 32023153801300001 BIB 5 9 3153801300002 REACTION 1(95-AM-243(N,F),,NU,,EPI,DERIV) 3153801300003 2(95-AM-243(N,F),,AP,LF,EPI) 3153801300004 3(95-AM-243(N,F),,AP,HF,EPI) 3153801300005 ANALYSIS The average emitted neutron number is 3153801300006 (nu = AF -AL - AH), where AF - compound nucleus mass; 3153801300007 AL - average light mass; AH - average heavy mass 3153801300008 ERR-ANALYS (DATA-ERR) No information on sources of uncertainty. 3153801300009 STATUS (TABLE) Table VIII of Nucl.Sci.Eng 135(2000)227 3153801300010 HISTORY (20210923A) VS. SF8:FIS->EPI STATUS moved from 001 3153801300011 ENDBIB 9 0 3153801300012 NOCOMMON 0 0 3153801300013 DATA 4 1 3153801300014 DATA 1DATA-ERR 1DATA 2DATA 3 3153801300015 PRT/FIS PRT/FIS NO-DIM NO-DIM 3153801300016 5.38 1.11 100.58 138.04 3153801300017 ENDDATA 3 0 3153801300018 ENDSUBENT 17 0 3153801399999 SUBENT 31538014 20211005 32023153801400001 BIB 5 9 3153801400002 REACTION 1(96-CM-244(N,F),,NU,,EPI,DERIV) 3153801400003 2(96-CM-244(N,F),,AP,LF,EPI) 3153801400004 3(96-CM-244(N,F),,AP,HF,EPI) 3153801400005 ANALYSIS The average emitted neutron number is 3153801400006 (nu = AF -AL - AH), where AF - compound nucleus mass; 3153801400007 AL - average light mass; AH - average heavy mass 3153801400008 ERR-ANALYS (DATA-ERR) No information on sources of uncertainty. 3153801400009 STATUS (TABLE) Table VIII of Nucl.Sci.Eng 135(2000)227 3153801400010 HISTORY (20210923A) VS. SF8:FIS->EPI STATUS moved from 001 3153801400011 ENDBIB 9 0 3153801400012 NOCOMMON 0 0 3153801400013 DATA 4 1 3153801400014 DATA 1DATA-ERR 1DATA 2DATA 3 3153801400015 PRT/FIS PRT/FIS NO-DIM NO-DIM 3153801400016 6.63 1.23 100.69 137.68 3153801400017 ENDDATA 3 0 3153801400018 ENDSUBENT 17 0 3153801499999 ENDENTRY 14 0 3153899999999