ENTRY O0723 20000427 0000O072300000001 SUBENT O0723001 20000427 0000O072300100001 BIB 14 49 O072300100002 TITLE Yields of Some Light-Mass Nuclides Produced in the O072300100003 Proton-Induced Fission of U-238. O072300100004 AUTHOR (A.H.KHAN, G.B.SAHA, L.YAFFE) O072300100005 INSTITUTE (1CANMCG) O072300100006 REFERENCE (J,CJC,46,3565,1968) O072300100007 HISTORY (20000313C) O072300100008 (20000313U) Last checking has been done. O072300100009 (20000427A) DATE is corrected O072300100010 SAMPLE The Uranium foils of normal isotopic distribution O072300100011 having a superficial density of about 140 mg/cm**2. O072300100012 Prior to irradiation the Uranium target foil was O072300100013 cleaned with nitric acid to remove the oxide layer.The O072300100014 foils was then sandwiched between two similarly treatedO072300100015 foils to compensate for recoil losses.A Copper monitor O072300100016 foil (21.44 MG/CM**2), similarly guarded with two otherO072300100017 Copper foils, was properly aligned with the target O072300100018 stack. O072300100019 FACILITY (SYNCY,1CANMCG) O072300100020 MONITOR ((MONIT)29-CU-65(P,X)29-CU-64,,SIG) O072300100021 DETECTOR (PROPC) A Low-Background B- Proportional Counter with O072300100022 A Background of Less Than 1 Count Per Minute. The O072300100023 Efficiency of the Beta Counter was Obtained For All O072300100024 Nuclides, Except Fo Ga-68 and Ga-70, by Calibration O072300100025 Against a 4-Pi Counter. The Efficiency For Ga-68 and O072300100026 Ga-70 was Taken to be the Same As That Ga-73. O072300100027 METHOD (CHSEP) O072300100028 (ACTIV) Irradiation Time Varied from 2-Min. To 60 Min.,O072300100029 Depending on the Activity and Bombarding Energy O072300100030 Desired. O072300100031 (INTB) O072300100032 (SITA) O072300100033 STATUS (TABLE) O072300100034 ADD-RES (Z-DIS) O072300100035 ANALYSIS (DECAY) O072300100036 ERR-ANALYS The limits shown in the Cross Section values determinedO072300100037 in the present work were compounded from the O072300100038 uncertainties in the Decay Curve analysis, O072300100039 determination of Chemical Yields, Target Thicknesses O072300100040 And Counter Efficiencies and were estimated to be 20% O072300100041 for Ni-66, Cu-67, Zn-72, Ga-72 and Ga-73. Because of O072300100042 the large uncertainty in the determination of the O072300100043 activities of Ga-68 and Ga-70, no limits have been O072300100044 quoted for these nuclides. Cross Sections for Ga-68 O072300100045 and Ga-70 appear to be relatively high. Because of theO072300100046 short half-Lives these have been obtained by quick O072300100047 chemical separation of Gallium samples, probably O072300100048 without sufficient purification and these discrepanciesO072300100049 are undoubtedly due to the presence of interfering O072300100050 nuclides. O072300100051 ENDBIB 49 0 O072300100052 NOCOMMON 0 0 O072300100053 ENDSUBENT 52 0 O072300199999 SUBENT O0723002 20000427 0000O072300200001 BIB 5 10 O072300200002 REACTION (92-U-238(P,F)28-NI-66,CUM,SIG) O072300200003 RAD-DET (29-CU-66,B-) O072300200004 DECAY-DATA (28-NI-66,55.HR,B-,200.,1.) OO072300200005 (29-CU-66,5.1MIN,B-,1590.,,B-,2630.) It is Daughter O072300200006 Ni-66. O072300200007 ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. O072300200008 COMMENT *by Authors* the Activity of the Nuclide was Measured O072300200009 With a 200 mg/cm**2 Thick Aluminum Absorber So That AllO072300200010 Low-Energy Beta Radiations were Stopped and Thus O072300200011 Self-Absorption Correction Could be Avoided. O072300200012 ENDBIB 10 0 O072300200013 NOCOMMON 0 0 O072300200014 DATA 4 7 O072300200015 EN DATA ERR-T MONIT O072300200016 MEV MB MB MB O072300200017 20. 0.006 0.001 260. O072300200018 30. 0.021 0.004 390. O072300200019 50. 0.12 0.02 210. O072300200020 60. 0.16 0.03 180. O072300200021 70. 0.24 0.05 160. O072300200022 77. 0.25 0.05 150. O072300200023 85. 0.32 0.06 140. O072300200024 ENDDATA 9 0 O072300200025 ENDSUBENT 24 0 O072300299999 SUBENT O0723003 20000427 0000O072300300001 BIB 2 2 O072300300002 REACTION (92-U-238(P,F)29-CU-67,CUM,SIG) O072300300003 ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. O072300300004 ENDBIB 2 0 O072300300005 NOCOMMON 0 0 O072300300006 DATA 4 8 O072300300007 EN DATA ERR-T MONIT O072300300008 MEV MB MB MB O072300300009 20. 0.017 0.003 260. O072300300010 30. 0.092 0.018 390. O072300300011 40. 0.17 0.03 260. O072300300012 50. 0.36 0.07 210. O072300300013 60. 0.56 0.11 180. O072300300014 70. 0.37 0.07 160. O072300300015 77. 0.58 0.12 150. O072300300016 85. 0.79 0.16 140. O072300300017 ENDDATA 10 0 O072300300018 ENDSUBENT 17 0 O072300399999 SUBENT O0723004 20000427 0000O072300400001 BIB 5 10 O072300400002 REACTION (92-U-238(P,F)30-ZN-72,CUM,SIG) O072300400003 RAD-DET (31-GA-72,B-) O072300400004 DECAY-DATA (30-ZN-72,46.5HR,B-,300.) O072300400005 (31-GA-72,14.1HR,B-,960.,,B-,660.,,B-,3160.) O072300400006 It is Daughter Zn-72. O072300400007 COMMENT *by Authors* the Activity of the Nuclide was Measured O072300400008 With a 200 mg/cm**2 Thick Aluminum Absorber So That AllO072300400009 Low-Energy Beta Radiations were Stopped and Thus O072300400010 Self-Absorption Correction Could be Avoided. O072300400011 ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. O072300400012 ENDBIB 10 0 O072300400013 NOCOMMON 0 0 O072300400014 DATA 4 8 O072300400015 EN DATA ERR-T MONIT O072300400016 MEV MB MB MB O072300400017 20. 0.09 0.02 260. O072300400018 30. 0.27 0.05 390. O072300400019 40. 0.64 0.13 260. O072300400020 50. 0.93 0.19 210. O072300400021 60. 1.1 0.22 180. O072300400022 70. 1.47 0.29 160. O072300400023 77. 1.34 0.27 150. O072300400024 85. 1.61 0.32 140. O072300400025 ENDDATA 10 0 O072300400026 ENDSUBENT 25 0 O072300499999 SUBENT O0723005 20000427 0000O072300500001 BIB 5 8 O072300500002 REACTION (92-U-238(P,F)31-GA-72,IND,SIG) O072300500003 RAD-DET (31-GA-72,B-) O072300500004 DECAY-DATA (31-GA-72,14.1HR,B-,960.,,B-,660.,,B-,3160.) O072300500005 COMMENT *by Authors* in Order to Stop All Conversion Electrons O072300500006 Uniformly For All Sources, the Same 200 mg/cm**2 Thick O072300500007 Aluminum Absorber was Used While the Activities of O072300500008 Gallium Isotopes were Measured. O072300500009 ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. O072300500010 ENDBIB 8 0 O072300500011 NOCOMMON 0 0 O072300500012 DATA 4 8 O072300500013 EN DATA ERR-T MONIT O072300500014 MEV MB MB MB O072300500015 20. 0.005 0.001 260. O072300500016 30. 0.007 0.001 390. O072300500017 40. 0.025 0.005 260. O072300500018 50. 0.067 0.013 210. O072300500019 60. 0.12 0.02 180. O072300500020 70. 0.17 0.03 160. O072300500021 77. 0.17 0.03 150. O072300500022 85. 0.34 0.07 140. O072300500023 ENDDATA 10 0 O072300500024 ENDSUBENT 23 0 O072300599999 SUBENT O0723006 20000427 0000O072300600001 BIB 5 16 O072300600002 REACTION (92-U-238(P,F)31-GA-73,CUM,SIG) O072300600003 RAD-DET (31-GA-73,B-) O072300600004 DECAY-DATA (31-GA-73,4.86HR,B-,,1.) O072300600005 COMMENT - By Authors - Ga-73 Decays (100%) To the Isomeric O072300600006 State of Ge-73. This Isomeric Transition is Highly O072300600007 Internally Converted (~100%) And these Conversion O072300600008 Electrons would Also be Detected Along with the O072300600009 Activities of the Ga Isotopes to a Varying Degree O072300600010 Depending on the Thickness of the Sources. O072300600011 In Order to Stop All Conversion Electrons Uniformly ForO072300600012 All Sources, the Same 200 mg/cm**2 Thick Aluminum O072300600013 Absorber was Used While the Activities of Gallium O072300600014 Isotopes were Measured. O072300600015 - By Compiler - According to ENSDF-99, Ge-73 has not anO072300600016 Isomeric State. O072300600017 ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. O072300600018 ENDBIB 16 0 O072300600019 NOCOMMON 0 0 O072300600020 DATA 4 8 O072300600021 EN DATA ERR-T MONIT O072300600022 MEV MB MB MB O072300600023 20. 0.081 0.016 260. O072300600024 30. 0.22 0.04 390. O072300600025 40. 0.57 0.12 260. O072300600026 50. 0.45 0.09 210. O072300600027 60. 0.88 0.18 180. O072300600028 70. 1.23 0.25 160. O072300600029 77. 1.24 0.25 150. O072300600030 85. 1.44 0.29 140. O072300600031 ENDDATA 10 0 O072300600032 ENDSUBENT 31 0 O072300699999 SUBENT O0723007 20000427 0000O072300700001 BIB 2 13 O072300700002 REACTION (92-U-238(P,F)31-GA-68,IND,SIG) O072300700003 COMMENT *by Authors* O072300700004 1. In Order to Stop All Conversion Electrons UniformlyO072300700005 For All Sources, the Same 200 mg/cm**2 Thick Aluminum O072300700006 Absorber was Used While the Activities of Gallium O072300700007 Isotopes were Measured. O072300700008 2. Cross Section For Ga-68 Appears to be Relatively O072300700009 High. Because of the Short Half-Life, the has Been O072300700010 Obtained by Quick Chemical Separation of Gallium O072300700011 Samples, Probably Without Sufficient Purification and O072300700012 The Discrepancy is Undoubtedly Due to the Presence of O072300700013 Interfering Nuclides. The Cross Sections Should be O072300700014 Regarded As Upper Limit Only. O072300700015 ENDBIB 13 0 O072300700016 NOCOMMON 0 0 O072300700017 DATA 3 2 O072300700018 EN DATA-MAX MONIT O072300700019 MEV MB MB O072300700020 70. 0.05 160. O072300700021 77. 0.24 150. O072300700022 ENDDATA 4 0 O072300700023 ENDSUBENT 22 0 O072300799999 SUBENT O0723008 20000427 0000O072300800001 BIB 2 13 O072300800002 REACTION (92-U-238(P,F)31-GA-70,IND,SIG) O072300800003 COMMENT *by Authors* O072300800004 1. In Order to Stop All Conversion Electrons UniformlyO072300800005 For All Sources, the Same 200 mg/cm**2 Thick Aluminum O072300800006 Absorber was Used While the Activities of Gallium O072300800007 Isotopes were Measured. O072300800008 2. Cross Section For Ga-70 Appears to be Relatively O072300800009 High. Because of the Short Half-Life, the has Been O072300800010 Obtained by Quick Chemical Separation of Gallium O072300800011 Samples, Probably Without Sufficient Purification and O072300800012 The Discrepancy is Undoubtedly Due to the Presence of O072300800013 Interfering Nuclides. The Cross Sections Should be O072300800014 Regarded As Upper Limit Only. O072300800015 ENDBIB 13 0 O072300800016 NOCOMMON 0 0 O072300800017 DATA 3 3 O072300800018 EN DATA-MAX MONIT O072300800019 MEV MB MB O072300800020 70. 0.37 160. O072300800021 77. 0.52 150. O072300800022 85. 0.82 140. O072300800023 ENDDATA 5 0 O072300800024 ENDSUBENT 23 0 O072300899999 ENDENTRY 8 0 O072399999999