ENTRY 22466 20160820 22522246600000001 SUBENT 22466001 20160820 22522246600100001 BIB 18 99 2246600100002 TITLE Excitation functions of neutron induced reactions 2246600100003 on some isotopes of zinc, gallium and germanium 2246600100004 in the energy range of 6.2 to 12.4 MeV 2246600100005 AUTHOR (C.Nesaraja, K.-H.Linse, S.Spellerberg, S.Sudar, 2246600100006 A.Suhaimi, J.Csikai, A.Fessler, S.M.Qaim) 2246600100007 INSTITUTE (2GERJUL) Qaim, Linse, Spellerberg, and 2246600100008 Experimental Site 2246600100009 (2ZZZGEL) Fessler 2246600100010 (3HUNKOS) Sudar, Csikai 2246600100011 (3MALUKM) Nesaraja, Suhaimi 2246600100012 REFERENCE (J,RCA,86,(1),1,1999) Main Reference 2246600100013 (R,JUEL-3550,15,199806) Abstracts 2246600100014 REL-REF (I,,S.M.Qaim+,J,NSE,88,143,1984) Target and geometry 2246600100015 of D(d,n)He-3 neutron source 2246600100016 (M,22159001,S.M.Qaim+,J,PR/C,40,1993,1989) Exp. details2246600100017 (M,22406001,A.Fessler+,J,PR/C,58,996,1998) Exp. details2246600100018 FACILITY (CYCLO,2GERJUL) Variable energy compact Cyclotron CV282246600100019 METHOD (ACTIV) Activation technique in combination with 2246600100020 (GSPEC) non-destructive gamma-ray and X-ray spectrum. 2246600100021 (STTA) Stack of samples and aluminum/niobium 2246600100022 monitor foils 2246600100023 (CHSEP) Radiochemical separation 2246600100024 INC-SOURCE (D-D) 2H(d,n)3He reaction for 7.5-12.3 MeV En-range 2246600100025 using D2 gas target 2246600100026 DETECTOR (HPGE) For Al/Fe and some reaction products activity 2246600100027 measurement 2246600100028 (PROPC) For beta- detection 2Pi gas flow proportional 2246600100029 counter was used 2246600100030 PART-DET (DG,B-) 2246600100031 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2246600100032 The neutron flux density effective during each 2246600100033 irradiation was determined via the monitor reaction 2246600100034 27Al(n,alpha)24Na 2246600100035 (13-AL-27(N,P)12-MG-27,,SIG) 2246600100036 In short irradiations of about 5 min duration, the 2246600100037 neutron flux density was measured via the reaction 2246600100038 27Al(n,p)27Mg 2246600100039 (26-FE-56(N,P)25-MN-56,,SIG) 2246600100040 At low neutron energies the neutron flux density 2246600100041 effective during each irradiation was determined via 2246600100042 the monitor reaction 56Fe(n,p)56Mn 2246600100043 DECAY-MON (11-NA-24,14.97HR,DG,1369.0,1.0) 2246600100044 (12-MG-27,9.46MIN,DG,844.,0.73) 2246600100045 (25-MN-56,2.58HR,DG,847.,0.989) 2246600100046 MONIT-REF (,N.P.Kocherov+,R,IAEA-NDS-141,1993) 2246600100047 SAMPLE .High-purity (99.9%) Of natural and enriched isotopic 2246600100048 compositions were used either in the form of elements 2246600100049 (Ge and Zn) or simple compounds(Ge-O2, Ga-O2, Zn-O). 2246600100050 The enriched 74Ge as 74Ge-O2 and 71Ga as 71Ga2-O3 had 2246600100051 isotopic composition 98.44% and 99.54%. 2246600100052 .Samples of Ge, Ga2-O3, Zn-O and Zn of natural isotopic2246600100053 abundance were prepared in the form of pellets 20 mm 2246600100054 diameter and 3 mm thickness, weight 2 and 4 gram, 2246600100055 placed in aluminum capsule 2246600100056 .Aluminum and iron foils for neutron background 2246600100057 determination 2246600100058 CORRECTION .Gas-out irradiations were done with Al and Fe foils 2246600100059 to establish correction factors for neutron back- 2246600100060 ground using 27Al(n,p)27Mg, 27Al(n,alpha)24Na and 2246600100061 55Fe(n,p)55Mn reactions. 2246600100062 .Corrections were made also for 2246600100063 -Emission probabilities of beta and gamma-rays 2246600100064 -Neutron flux fluctuations during irradiations 2246600100065 -Coincidence losses, gamma-ray abundance 2246600100066 -Beta and gamma-ray self-absorption 2246600100067 -Detector efficiency 2246600100068 -Yield of chemical separation sources 2246600100069 ADD-RES (THEO,COMP) Nuclear Model Calculations 2246600100070 ERR-ANALYS (ERR-T) Total error equal to square root from all 2246600100071 the partial errors given below 2246600100072 (ERR-S,1.,10.) Statistical error for beta-, gamma-ray 2246600100073 spectrometry. 2246600100074 (ERR-1,2.,3.) Error of neutron energy determination 2246600100075 (ERR-2,,1.) Max error of sample weight. 2246600100076 (ERR-3) Error of irradiation geometry 2246600100077 (ERR-4) Error of irradiation time 2246600100078 (ERR-5) Error of peak area analysis for gamma- 2246600100079 spectrometry. 2246600100080 (ERR-6,10.,15.) Error of decay-curve analysis for beta 2246600100081 spectrometry. 2246600100082 (ERR-7) Error of the efficiency of detector in 2246600100083 gamma-ray spectrometry. 2246600100084 (ERR-8) Error of the efficiency of detector in 2246600100085 beta spectrometry. 2246600100086 (ERR-9,1.,10.) Error of correction for activity induced2246600100087 by background neutrons 2246600100088 (ERR-10) Error of decay data 2246600100089 (ERR-12,3.,5.) Error of coincidence summing 2246600100090 correction in gamma-ray spectrometry. 2246600100091 (MONIT-ERR,3.,5.) Error of reference cross sections 2246600100092 .EN-RSL - Energy spread due to the large angle of 2246600100093 emission and the finite size of sample 2246600100094 HISTORY (20000323C) + + Compiled by SM 2246600100095 (20000324U) Last checking has been done. 2246600100096 (20121015U) Correction of a typo in author name 2246600100097 ERR-ANALYS was updated. 2246600100098 (20160820A) SD: DECAY-DATA corrected in Subents 007,0082246600100099 DATA values were corrected following presentation in 2246600100100 the Tables (truncated zeros were added). 2246600100101 ENDBIB 99 0 2246600100102 COMMON 6 3 2246600100103 ERR-3 ERR-4 ERR-5 ERR-7 ERR-8 ERR-10 2246600100104 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2246600100105 3. 0.1 3. 5. 15. 1.2246600100106 ENDCOMMON 3 0 2246600100107 ENDSUBENT 106 0 2246600199999 SUBENT 22466002 20160820 22522246600200001 BIB 3 4 2246600200002 REACTION (32-GE-73(N,P)31-GA-73,,SIG) 2246600200003 DECAY-DATA (31-GA-73,4.87HR,B-,,1.0, 2246600200004 DG,297.3,0.798) 2246600200005 STATUS (TABLE) From Table 3 of RCA,86,1,1999 2246600200006 ENDBIB 4 0 2246600200007 NOCOMMON 0 0 2246600200008 DATA 4 8 2246600200009 EN EN-RSL DATA ERR-T 2246600200010 MEV MEV MB MB 2246600200011 7.46 0.26 2.26 0.34 2246600200012 8.28 0.27 2.62 0.40 2246600200013 9.16 0.55 4.16 0.63 2246600200014 9.96 0.34 7.08 1.06 2246600200015 10.71 0.35 7.72 0.80 2246600200016 11.37 0.38 8.50 1.41 2246600200017 11.80 0.31 9.74 1.20 2246600200018 11.96 0.7 13.97 2.10 2246600200019 ENDDATA 10 0 2246600200020 ENDSUBENT 19 0 2246600299999 SUBENT 22466003 20160820 22522246600300001 BIB 4 8 2246600300002 REACTION (31-GA-71(N,P)30-ZN-71-M,,SIG) 2246600300003 DECAY-DATA (30-ZN-71-M,3.94HR,B-,1483.,1.0, 2246600300004 DG,386.4,0.93) 2246600300005 FLAG (1.) Irradiated samples at this energy were 2246600300006 radiochemically processed 2246600300007 (2.) Data from Table 3 2246600300008 (3.) Data from Table 4 2246600300009 STATUS (TABLE) From Table 3,4 of RCA,86,1,1999 2246600300010 ENDBIB 8 0 2246600300011 NOCOMMON 0 0 2246600300012 DATA 6 12 2246600300013 EN EN-RSL DATA ERR-T FLAG FLAG 2246600300014 MEV MEV MB MB NO-DIM NO-DIM 2246600300015 6.32 0.41 0.45 0.07 1. 2.2246600300016 6.32 0.41 0.14 0.04 1. 3.2246600300017 7.33 0.48 0.82 0.12 1. 2.2246600300018 7.33 0.48 0.12 0.04 1. 3.2246600300019 8.01 0.53 1.49 0.21 1. 2.2246600300020 8.01 0.53 3.06 0.77 1. 3.2246600300021 9.09 0.62 2.53 0.35 1. 2.2246600300022 9.09 0.62 4.67 1.17 1. 3.2246600300023 10.13 0.74 4.70 0.69 1. 2.2246600300024 11.24 0.84 7.40 1.55 1. 2.2246600300025 12.06 0.93 8.19 1.50 2.2246600300026 12.06 0.93 9.34 2.09 1. 2.2246600300027 ENDDATA 14 0 2246600300028 ENDSUBENT 27 0 2246600399999 SUBENT 22466004 20160820 22522246600400001 BIB 3 4 2246600400002 REACTION (30-ZN-67(N,P)29-CU-67,,SIG) 2246600400003 DECAY-DATA (29-CU-67,2.58D,B-,,1.0, 2246600400004 DG,184.6,0.486) 2246600400005 STATUS (TABLE) From Table 3 of RCA,86,1,1999 2246600400006 ENDBIB 4 0 2246600400007 NOCOMMON 0 0 2246600400008 DATA 4 7 2246600400009 EN EN-RSL DATA ERR-T 2246600400010 MEV MEV MB MB 2246600400011 6.24 0.42 5.51 0.70 2246600400012 7.16 0.48 7.84 0.80 2246600400013 8.16 0.56 13.12 1.40 2246600400014 9.28 0.32 13.45 1.50 2246600400015 10.23 0.34 15.33 2.10 2246600400016 11.15 0.40 22.64 3.52 2246600400017 12.08 0.93 26.49 5.27 2246600400018 ENDDATA 9 0 2246600400019 ENDSUBENT 18 0 2246600499999 SUBENT 22466005 20160820 22522246600500001 BIB 3 4 2246600500002 REACTION (30-ZN-68(N,A)28-NI-65,,SIG) 2246600500003 DECAY-DATA (28-NI-65,2.50HR,B-,,1.0, 2246600500004 DG,1481.9,0.235) 2246600500005 STATUS (TABLE) From Table 3 of RCA,86,1,1999 2246600500006 ENDBIB 4 0 2246600500007 NOCOMMON 0 0 2246600500008 DATA 4 7 2246600500009 EN EN-RSL DATA ERR-T 2246600500010 MEV MEV MB MB 2246600500011 6.24 0.42 0.71 0.08 2246600500012 7.16 0.48 1.81 0.20 2246600500013 8.16 0.56 3.49 0.38 2246600500014 9.28 0.32 2.78 0.31 2246600500015 10.23 0.34 3.36 0.35 2246600500016 11.15 0.40 4.31 0.48 2246600500017 12.08 0.93 4.80 0.51 2246600500018 ENDDATA 9 0 2246600500019 ENDSUBENT 18 0 2246600599999 SUBENT 22466006 20160820 22522246600600001 BIB 4 5 2246600600002 REACTION (32-GE-70(N,P)31-GA-70,,SIG) 2246600600003 DECAY-DATA (31-GA-70,21.2MIN,B-,1656.,0.996) 2246600600004 FLAG (1.) Irradiated Samples at this energy were 2246600600005 radiochemically processed 2246600600006 STATUS (TABLE) From Table 4 of RCA,86,1,1999 2246600600007 ENDBIB 5 0 2246600600008 NOCOMMON 0 0 2246600600009 DATA 5 9 2246600600010 EN EN-RSL DATA ERR-T FLAG 2246600600011 MEV MEV MB MB NO-DIM 2246600600012 6.35 0.21 20.0 4.7 2246600600013 7.38 0.21 31.0 7.8 2246600600014 8.38 0.27 39.8 9.2 2246600600015 9.34 0.24 37.0 8.6 2246600600016 10.05 0.67 56.3 9.9 1. 2246600600017 10.29 0.26 42.8 9.9 2246600600018 10.96 0.75 64.4 22.9 1. 2246600600019 11.24 0.28 62.2 19.7 2246600600020 11.87 0.83 69.8 23.7 1. 2246600600021 ENDDATA 11 0 2246600600022 ENDSUBENT 21 0 2246600699999 SUBENT 22466007 20160820 22522246600700001 BIB 5 5 2246600700002 REACTION (32-GE-74(N,P)31-GA-74,,SIG) 2246600700003 DECAY-DATA (31-GA-74-G,8.1MIN,B-,2420.,1.0) 2246600700004 SAMPLE .Enriched 74Ge was used 2246600700005 STATUS (TABLE) From Table 4 of RCA,86,1,1999 2246600700006 HISTORY (20160820A) SD: All parameters of DECAY-DATA corrected 2246600700007 ENDBIB 5 0 2246600700008 NOCOMMON 0 0 2246600700009 DATA 4 4 2246600700010 EN EN-RSL DATA ERR-T 2246600700011 MEV MEV MB MB 2246600700012 9.44 0.49 1.50 0.32 2246600700013 10.45 0.55 3.12 0.63 2246600700014 11.48 0.64 4.01 1.08 2246600700015 12.44 0.68 6.03 1.61 2246600700016 ENDDATA 6 0 2246600700017 ENDSUBENT 16 0 2246600799999 SUBENT 22466008 20160820 22522246600800001 BIB 5 5 2246600800002 REACTION (31-GA-71(N,2N)31-GA-70,,SIG) 2246600800003 DECAY-DATA (31-GA-70,21.2MIN,B-,1656.,0.996) 2246600800004 SAMPLE .Enriched 71Ga was used 2246600800005 STATUS (TABLE) From Table 4 of RCA,86,1,1999 2246600800006 HISTORY (20160820A) SD: hl, intensity of DECAY-DATA corrected 2246600800007 ENDBIB 5 0 2246600800008 NOCOMMON 0 0 2246600800009 DATA 4 4 2246600800010 EN EN-RSL DATA ERR-T 2246600800011 MEV MEV MB MB 2246600800012 9.44 0.49 11.6 2.1 2246600800013 10.45 0.55 233. 35. 2246600800014 11.48 0.64 589. 137. 2246600800015 12.44 0.68 877. 203. 2246600800016 ENDDATA 6 0 2246600800017 ENDSUBENT 16 0 2246600899999 ENDENTRY 8 0 2246699999999