ENTRY 21552 20201222 22962155200000001 SUBENT 21552001 20201222 22962155200100001 BIB 17 58 2155200100002 TITLE Independent yields of 150Pm in the thermal neutron 2155200100003 induced fission of 233U, 235U, 239Pu and 249Cf and 2155200100004 cross section for the 149Pm(n,gamma)150Pm reaction 2155200100005 AUTHOR (H.Gaeggeler,H.R.Von Gunten,H.S.Pruys) 2155200100006 REFERENCE (J,JIN,38,205,1976) main ref. 2155200100007 (T,GAEGGELER,197312) Thesis, Univ of Bern. 2155200100008 (C,73ROCH,2,475,1973) Preliminary, superseded. 2155200100009 (P,INDC(SEC)-36,63,1973) Preliminary, superseded. 2155200100010 (P,INDC(SWT)-4,15,1973) 2155200100011 (J,HPA,46,445(1),1973) Abstract 2155200100012 COMMENT Preliminary yields were not corrected for contributions2155200100013 by the second order reaction and deviate from the 2155200100014 values given here. 2155200100015 INSTITUTE (2SWTUBE) 2155200100016 (2SWTWUR) H.S.P. and site of reactor irradiation. 2155200100017 (2GERMNZ) Triga reactor for Cf-249 irradiation. 2155200100018 FACILITY (REAC,2SWTWUR) Swimming pool reactor, SAPHIR 2155200100019 (REAC,2GERMNZ) Cf-249 irradiation in TRIGA Mark II 2155200100020 INC-SOURCE (REAC) SAPHIR: Irradiation was 6.0 hr in a preliminary 2155200100021 measurements and 5-10 min in a subsequent experiments. 2155200100022 Thermal flux was 3 to 5 x 10*13 n/cm*2/sec. 2155200100023 TRIGA: Irradiation was 6.0 hr and thermal flux 2155200100024 was 6 x 10*11 n/cm*2/sec. 2155200100025 INC-SPECT Maxwellian thermal neutron spectrum. 2155200100026 SAMPLE In a preliminary set of experiments solutions of 2155200100027 uranium and plutonium (10-30/ug) were evaporated and 2155200100028 wrapped in aluminium foils. 2155200100029 For subsequent experiments 1-10 mg samples of uranium 2155200100030 and plutonium oxides (sealed in aluminium or quartz 2155200100031 tubes) were used. 2155200100032 METHOD (ACTIV,CHSEP) Measurement of gamma activity after 2155200100033 chemical separation of promethium. 2155200100034 DETECTOR (GELI) a 50. cm3 coaxial Ge(Li)-gamma spectrometer was 2155200100035 used in experiments with uranium and plutonium and 2155200100036 calibrated Ge(Li) detector, 44. cm3, coaxial, was used 2155200100037 in experiments with 249Cf. 2155200100038 ANALYSIS Values given are weighted means of several independent2155200100039 measurements. 2155200100040 CORRECTION Corrected for second order neutron capture reactions. 2155200100041 This data supersedes the uncorrected values 2155200100042 published before (see references). 2155200100043 ADD-RES Values of the measured independent yield divided by 2155200100044 the chain yield in the literature (see REL-REF) are 2155200100045 presented. 2155200100046 REL-REF (N,,M.E.Meek+,R,NEDO-12154-1,1974) 2155200100047 Chain yields used for ration calculation (see ADD-RES)2155200100048 ERR-ANALYS (ERR-T) Quoted uncertainties include 2155200100049 * statistical uncertainties at one standard deviation,2155200100050 * uncertainties in decay schemes, 2155200100051 but no contribution from errors on the half lives of2155200100052 Pm-150 or Pm-151. 2155200100053 * uncertainties in chain yields 2155200100054 (ERR-1) uncertainties due to detector calibration 2155200100055 HISTORY (19800604C) 2155200100056 (20201222A) SD:Updated to new date formats, lower case.2155200100057 Major corrections in all Subents. Several refs added. 2155200100058 Subents 003, 005, 007, 009 deleted (not measured, 2155200100059 information moved to ADD-RES). 2155200100060 ENDBIB 58 0 2155200100061 COMMON 2 3 2155200100062 EN-DUMMY ERR-1 2155200100063 EV PER-CENT 2155200100064 2.530E-02 5. 2155200100065 ENDCOMMON 3 0 2155200100066 ENDSUBENT 65 0 2155200199999 SUBENT 21552002 20201222 22962155200200001 BIB 5 7 2155200200002 REACTION (92-U-233(N,F)61-PM-150,IND,FY,,MXW) 2155200200003 DECAY-DATA (61-PM-150,2.7HR,DG,1165.,,DG,1325.,,DG,1736.) 2155200200004 SAMPLE (92-U-233,ENR=0.9991) 2155200200005 233U - 99.91%; 234U - 0.025%; 238U - 0.063% 2155200200006 STATUS (TABLE) Tbl.5 from J.Inorg.Nucl.Chem.,38,(1976)205 2155200200007 HISTORY (20201222U) SD: SAMPLE added; STATUS updated. 2155200200008 DATA-ERR -> ERR-T. 2155200200009 ENDBIB 7 0 2155200200010 NOCOMMON 0 0 2155200200011 DATA 2 1 2155200200012 DATA ERR-T 2155200200013 PC/FIS PC/FIS 2155200200014 2.6E-04 0.2E-04 2155200200015 ENDDATA 3 0 2155200200016 ENDSUBENT 15 0 2155200299999 NOSUBENT 21552003 20201222 22962155200300001 SUBENT 21552004 20201222 22962155200400001 BIB 5 7 2155200400002 REACTION (92-U-235(N,F)61-PM-150,IND,FY,,MXW) 2155200400003 SAMPLE (92-U-235,ENR=0.99613) 234U - 0.061%; 2155200400004 235U - 99.613%; 236U - 0.065%; 238U - 0.258% 2155200400005 DECAY-DATA (61-PM-150,2.7HR,DG,1165.,,DG,1325.,,DG,1736.) 2155200400006 STATUS (TABLE) Tbl.5 from J.Inorg.Nucl.Chem.,38,(1976)205 2155200400007 HISTORY (20201222U) SD: SAMPLE added; STATUS updated. 2155200400008 DATA-ERR -> ERR-T. 2155200400009 ENDBIB 7 0 2155200400010 NOCOMMON 0 0 2155200400011 DATA 2 1 2155200400012 DATA ERR-T 2155200400013 PC/FIS PC/FIS 2155200400014 3.0E-05 1.0E-05 2155200400015 ENDDATA 3 0 2155200400016 ENDSUBENT 15 0 2155200499999 NOSUBENT 21552005 20201222 22962155200500001 SUBENT 21552006 20201222 22962155200600001 BIB 5 7 2155200600002 REACTION (94-PU-239(N,F)61-PM-150,IND,FY,,MXW) 2155200600003 DECAY-DATA (61-PM-150,2.7HR,DG,1165.,,DG,1325.,,DG,1736.) 2155200600004 SAMPLE (94-PU-239,ENR=0.92087) 2155200600005 239Pu - 92.087%; 2240Pu - 7.351%; 241Pu - 0.563% 2155200600006 STATUS (TABLE) Tbl.5 from J.Inorg.Nucl.Chem.,38,(1976)205 2155200600007 HISTORY (20201222U) SD: SAMPLE added; STATUS updated. 2155200600008 DATA-ERR -> ERR-T. 2155200600009 ENDBIB 7 0 2155200600010 NOCOMMON 0 0 2155200600011 DATA 2 1 2155200600012 DATA ERR-T 2155200600013 PC/FIS PC/FIS 2155200600014 1.150E-03 7.0E-05 2155200600015 ENDDATA 3 0 2155200600016 ENDSUBENT 15 0 2155200699999 NOSUBENT 21552007 20201222 22962155200700001 SUBENT 21552008 20201222 22962155200800001 BIB 5 12 2155200800002 REACTION (98-CF-249(N,F)61-PM-150,IND,FY,,MXW) 2155200800003 SAMPLE An isotopically clean recoil source of Cf-249 2155200800004 of about 10 ug was used in the Mainz irradiation. 2155200800005 The irradiation time was 6.0 hr and the thermal neutron2155200800006 flux 6 x 10**11/cm/sec. The fission fragments recoiling2155200800007 from the 249Cf-target were collected in a layer of 2155200800008 ammonium nitrate. The target was protected against 2155200800009 self-transfer of 249Cf by a 10. ug layer of aluminium. 2155200800010 DECAY-DATA (61-PM-150,2.7HR,DG,1165.,,DG,1325.,,DG,1736.) 2155200800011 STATUS (TABLE) Tbl.5 from J.Inorg.Nucl.Chem.,38,(1976)205 2155200800012 HISTORY (20201222U) SD: SAMPLE added; STATUS updated. 2155200800013 DATA-ERR -> ERR-T. 2155200800014 ENDBIB 12 0 2155200800015 NOCOMMON 0 0 2155200800016 DATA 2 1 2155200800017 DATA ERR-T 2155200800018 PC/FIS PC/FIS 2155200800019 1.90E-02 2.0E-03 2155200800020 ENDDATA 3 0 2155200800021 ENDSUBENT 20 0 2155200899999 NOSUBENT 21552009 20201222 22962155200900001 SUBENT 21552010 20201222 22962155201000001 BIB 5 7 2155201000002 REACTION (61-PM-149(N,G)61-PM-150,,SIG,,MXW) Cross section. 2155201000003 DECAY-DATA (61-PM-150,2.7HR,DG,1165.,,DG,1325.,,DG,1736.) 2155201000004 METHOD (ACTIV) Irradiation of 99.6% 235U, 6 hr with thermal 2155201000005 neutrons 2155201000006 STATUS (TABLE) Tbl.4 from J.Inorg.Nucl.Chem.,38,(1976)205 2155201000007 HISTORY (20201222U) SD: SAMPLE added; STATUS updated. 2155201000008 DATA-ERR -> ERR-T. ANALYSIS -> METHOD. 2155201000009 ENDBIB 7 0 2155201000010 NOCOMMON 0 0 2155201000011 DATA 2 1 2155201000012 DATA ERR-T 2155201000013 B B 2155201000014 1630. 160. 2155201000015 ENDDATA 3 0 2155201000016 ENDSUBENT 15 0 2155201099999 ENDENTRY 10 0 2155299999999