ENTRY 23353 20171020 22682335300000001 SUBENT 23353001 20171020 22682335300100001 BIB 14 34 2335300100002 REFERENCE (J,JIN,32,705,1970) 2335300100003 AUTHOR (P.del Marmol,D.C.Perricos) 2335300100004 TITLE Identification of 88Se and search for delayed neutron 2335300100005 emission from 87Se and 88Se 2335300100006 INSTITUTE (2BLGMOL) 2335300100007 REL-REF (M,,P.del Marmol+,J,RCA,12,57,1969) 2335300100008 Method of chemical separation 2335300100009 FACILITY (REAC,2BLGMOL) BR1 reactor 2335300100010 INC-SOURCE (REAC) 2335300100011 INC-SPECT Thermal neutron flux from 1.9E+11 to 1.1E+12 n/cm2/sec.2335300100012 SAMPLE 100 mg of U-235 ( 90% enrichment). dissolved in 2335300100013 1.25ml 40% H2SO(4), 0.1 ml of SeO(3)(2-) carrier (0.1mg2335300100014 Se) and 10.1 ml of Se-75 tracer dissolved in water. 2335300100015 METHOD (CHSEP) Chemical yields were measured by comparing 2335300100016 residual tracer activity with Se-75 standard in 2335300100017 NaI(Tl) crystal. 2335300100018 Extra purification step to remove Rb . 2335300100019 DETECTOR (HE3SP) Five He-3 counters in paraffin , connected to 2335300100020 T.M.C. 400-channel multiscaler. 2335300100021 (NAICR) 2335300100022 ANALYSIS (DECAY) Neutron decay curve analyzed 2335300100023 Data used in analysis : 2335300100024 Br-87: HL = 55.65sec, Pn=2.62+-0.05 %; 2335300100025 Br-88: HL=15.85 sec , Pn=4.7+-0.4 % , 2335300100026 from P.del Marmol. 2335300100027 Se-87:HL measured to be 5.9+-0.2sec. 2335300100028 Se-88 HL=1.1+-0.1sec ( at 3.05 sec irradiation time), 2335300100029 ~1.7sec ( at 5.05sec irradiation time) measured; 2335300100030 but conservative estimate 1.3+-0.3 sec was used. 2335300100031 ERR-ANALYS Errors in half-lives and initial activities resulted 2335300100032 from counting statistics, activity curve resolution, 2335300100033 chemical yield measurement; 2335300100034 separation time error +-0.8 sec. 2335300100035 HISTORY (20171020C) M.M. 2335300100036 ENDBIB 34 0 2335300100037 NOCOMMON 0 0 2335300100038 ENDSUBENT 37 0 2335300199999 SUBENT 23353002 20171020 22682335300200001 BIB 7 18 2335300200002 REACTION (92-U-235(N,F)34-SE-87,CUM,FY) 2335300200003 Cumulative fission yield of Se-87 2335300200004 DECAY-DATA (34-SE-87,5.9SEC) 5.9+-0.2 sec measured. 2335300200005 ANALYSIS Calculated from the ratio of the measured Se-87 2335300200006 activity to that of 55.65sec delayed neutron activity 2335300200007 of irradiated U-235, using for this neutron group 2335300200008 a fission yield 0.058+-0.007 % from G.R.Keepin, 2335300200009 Physics and Nuclear Kinetics, chap.4, Addison-Wesley, 2335300200010 Reading, 1965. 2335300200011 MONITOR (92-U-235(N,F),DL/GRP,NU) 2335300200012 Fission yield for 55.65 sec neutron group. 2335300200013 From: 2335300200014 G.R.Keepin,Physics and Nuclear Kinetics, chap.4, 2335300200015 Addison-Wesley, Reading,1965. 2335300200016 REL-REF (D,23350002,L.Tomlinson+,J,JIN,30,1995,1968) 2335300200017 1.17+-0.25 %/fis. 2335300200018 ERR-ANALYS (DATA-ERR) Not explained clear, see also Subent 001 2335300200019 STATUS (TABLE) Text, p. 708 of J.Inorg.Nucl.Chem.,32,705,1970 2335300200020 ENDBIB 18 0 2335300200021 COMMON 2 3 2335300200022 EN-DUMMY HL-NRM 2335300200023 EV SEC 2335300200024 0.0253 55.65 2335300200025 ENDCOMMON 3 0 2335300200026 DATA 4 1 2335300200027 DATA DATA-ERR MONIT MONIT-ERR 2335300200028 PC/FIS PC/FIS PC/FIS PC/FIS 2335300200029 0.65 0.13 0.058 0.007 2335300200030 ENDDATA 3 0 2335300200031 ENDSUBENT 30 0 2335300299999 SUBENT 23353003 20171020 22682335300300001 BIB 5 11 2335300300002 REACTION ((92-U-235(N,F)34-SE-87,DL/CUM,NU)/ 2335300300003 (92-U-235(N,F)35-BR-87,DL/CUM,NU)) 2335300300004 ANALYSIS Measured ratio of Se-87 neutron activity to that of 2335300300005 Br-87, extrapolated back to Se-Br separation time so as2335300300006 to obtain A9Se87,t1), where t1 is the interval between 2335300300007 the end of the irradiation and the Se-Br separation. 2335300300008 Average of 7 runs. 2335300300009 DECAY-DATA (34-SE-87,5.9SEC) 5.9+-0.2 sec measured. 2335300300010 (35-BR-87,55.65SEC) 2335300300011 ERR-ANALYS (DATA-ERR) Not explained clear, see also Subent 001 2335300300012 STATUS (TABLE) Text, p. 712 of J.Inorg.Nucl.Chem.,32,705,1970 2335300300013 ENDBIB 11 0 2335300300014 COMMON 1 3 2335300300015 EN-DUMMY 2335300300016 EV 2335300300017 0.0253 2335300300018 ENDCOMMON 3 0 2335300300019 DATA 2 1 2335300300020 DATA DATA-ERR 2335300300021 NO-DIM NO-DIM 2335300300022 0.74 0.22 2335300300023 ENDDATA 3 0 2335300300024 ENDSUBENT 23 0 2335300399999 SUBENT 23353004 20171020 22682335300400001 BIB 6 8 2335300400002 REACTION (34-SE-87(0,B-)35-BR-87,,PN) 2335300400003 DECAY-DATA (34-SE-87,5.9SEC) 5.9+-0.2 sec measured. 2335300400004 (35-BR-87,55.65SEC) 2335300400005 ASSUMED (ASSUM,35-BR-87(0,B-)36-KR-87,,PN) Pn=2.62+-0.05 % 2335300400006 REL-REF (R,,P.del Marmol,J,ND/A,6,141,1969) Br-87 HL and Pn. 2335300400007 ERR-ANALYS (DATA-ERR) Not explained clear, see also Subent 001 2335300400008 STATUS (TABLE) Text, p.712 of J.Inorg.Nucl.Chem.,32,705,1970 2335300400009 (DEP,23353003) Ratio of Se-87 to Br-87 activities. 2335300400010 ENDBIB 8 0 2335300400011 NOCOMMON 0 0 2335300400012 DATA 4 1 2335300400013 DATA DATA-ERR ASSUM ASSUM-ERR 2335300400014 NO-DIM NO-DIM NO-DIM NO-DIM 2335300400015 0.0023 0.0007 0.0262 0.0005 2335300400016 ENDDATA 3 0 2335300400017 ENDSUBENT 16 0 2335300499999 SUBENT 23353005 20171020 22682335300500001 BIB 6 11 2335300500002 REACTION (92-U-235(N,F)34-SE-87,DL/CUM,NU) 2335300500003 Delayed neutron yield for Se-87 2335300500004 DECAY-DATA (34-SE-87,5.9SEC) 5.9+-0.2 sec measured. 2335300500005 (35-BR-87,55.65SEC) 2335300500006 REL-REF (R,,P.del Marmol,J,ND/A,6,141,1969) Br-87 HL and Pn. 2335300500007 ANALYSIS Derived as the Se-87 cumulative fission yield 2335300500008 multiplied by neutron emission probability Pn . 2335300500009 ERR-ANALYS (DATA-ERR) Not explained clear, see also Subent 001 2335300500010 STATUS (TABLE) Text, p.712 of J.Inorg.Nucl.Chem.,32,705,1970 2335300500011 (DEP,23353004) Pn 2335300500012 (DEP,23353002) Se-87 cumulative fission yield. 2335300500013 ENDBIB 11 0 2335300500014 COMMON 1 3 2335300500015 EN-DUMMY 2335300500016 EV 2335300500017 0.0253 2335300500018 ENDCOMMON 3 0 2335300500019 DATA 2 1 2335300500020 DATA DATA-ERR 2335300500021 PC/FIS PC/FIS 2335300500022 0.15E-2 0.05E-2 2335300500023 ENDDATA 3 0 2335300500024 ENDSUBENT 23 0 2335300599999 SUBENT 23353006 20171020 22682335300600001 BIB 4 7 2335300600002 REACTION ((92-U-235(N,F)34-SE-88,DL/CUM,NU)/ 2335300600003 (92-U-235(N,F)35-BR-88,DL/CUM,NU)) 2335300600004 ANALYSIS Measured ratio of Se-88 neutron activity to that of 2335300600005 Br-88 extrapolated at Se-Br separation time . 2335300600006 DECAY-DATA (34-SE-88,1.3SEC) 1.3+-0.3 sec measured. 2335300600007 (35-BR-88,15.85SEC) 2335300600008 STATUS (TABLE) Text, p. 712 of J.Inorg.Nucl.Chem.,32,705,1970 2335300600009 ENDBIB 7 0 2335300600010 COMMON 1 3 2335300600011 EN-DUMMY 2335300600012 EV 2335300600013 0.0253 2335300600014 ENDCOMMON 3 0 2335300600015 DATA 1 1 2335300600016 DATA-APRX 2335300600017 NO-DIM 2335300600018 1.25 2335300600019 ENDDATA 3 0 2335300600020 ENDSUBENT 19 0 2335300699999 SUBENT 23353007 20171020 22682335300700001 BIB 6 13 2335300700002 REACTION (34-SE-88(0,B-)35-BR-88,,PN) 2335300700003 DECAY-DATA (34-SE-88,1.3SEC) 1.3+-0.3 sec measured. 2335300700004 (35-BR-88,15.85SEC) 2335300700005 ASSUMED (ASSUM,35-BR-88(0,B-)36-KR-88,,PN) Pn=4.7+-0.4 % 2335300700006 REL-REF (R,,P.del Marmol,J,ND/A,6,141,1969) Br-88 HL and Pn. 2335300700007 (A,,G.Herrmann,W,HERRMANN,1970) Private communication, 2335300700008 to be published. 2335300700009 COMMENT Of authors Pn value was obtained as 0.4 + 0.3 -0.15 %,2335300700010 however it's unreasonable to draw any firm conclusions 2335300700011 from so little evidence and an upper limit of Pn 1.% 2335300700012 was set. 2335300700013 STATUS (TABLE) Text, p.712 of J.Inorg.Nucl.Chem.,32,705,1970 2335300700014 (DEP,23353006) Ratio of Se-88 to Br-88 activities 2335300700015 ENDBIB 13 0 2335300700016 NOCOMMON 0 0 2335300700017 DATA 3 1 2335300700018 DATA-MAX ASSUM ASSUM-ERR 2335300700019 NO-DIM NO-DIM NO-DIM 2335300700020 0.01 0.047 0.004 2335300700021 ENDDATA 3 0 2335300700022 ENDSUBENT 21 0 2335300799999 ENDENTRY 7 0 2335399999999