ENTRY 31516 20211005 32023151600000001 SUBENT 31516001 20211005 32023151600100001 BIB 17 68 3151600100002 INSTITUTE (3ARGCAB) 3151600100003 REFERENCE (J,NSE,139,24,2001) Data, details on activity 3151600100004 measurements 3151600100005 (J,NSE,127,245,1997) Further details of the 3151600100006 experimental set-up 3151600100007 AUTHOR (M.A.Arribere,S.Ribeiro Guevara,P.M.Suarez, 3151600100008 A.J.Kestelman) 3151600100009 TITLE Threshold reaction cross sections of nickel isotopes, 3151600100010 averaged over a U-235 fission neutron spectrum 3151600100011 METHOD (ACTIV) Activation method with registration of 3151600100012 secondary gamma-ray spectra. Irradiation times were 3151600100013 not more than 20 min, to keep the burn up losses 3151600100014 negligible. Source-to-detector distances no closer than3151600100015 4.8 cm for short-lived activities (Co-60m, Co-61) and 3151600100016 Co-58g and detector dead time less than 5% (Co-60m, 3151600100017 Co-61) or 1% - Co-58g. 3 cm source-to-detector 3151600100018 distances for long-lived activities with dead time less3151600100019 than 0.2%. 3151600100020 FACILITY (REAC,3ARGCAB) 3151600100021 INC-SOURCE (REAC) Neutrons from RA-6 materials test reactor 3151600100022 at Centre Atomico Barilochi. 3151600100023 Compiler's note: The neutron flux characteristics of 3151600100024 this reactor as given in earlier publications (see 3151600100025 ENTRY 31511 for references) are the following: 3151600100026 thermal neutron flux about 6.0E+12 neutrons/cm**2/sec, 3151600100027 epithermal neutron flux about 3.0E+11 3151600100028 neutrons/cm**2/sec and fast neutron flux about 2.0E+12 3151600100029 neutrons/cm**2/sec 3151600100030 INC-SPECT Undisturbed U-235 fission spectrum. For details see 3151600100031 P.M. Suarez et al., Nucl. Sci. Eng., 127 (1997) p.245 3151600100032 DETECTOR (HPGE) 67 cm*3 ORTEC high-purity germanium intrinsic-N 3151600100033 coaxial detector with efficiency 12.3% relative to the 3151600100034 7.6*7.6-cm NaI(Tl) detector at 1.33 MeV and 25-cm 3151600100035 distance. 3151600100036 The detector absolute efficiency curve was obtained 3151600100037 with IAEA and NIST standard sources calibrated within 3151600100038 2 per-cent uncertainty. 3151600100039 SAMPLE About 0.25 mm-thick high purity foils (natural Ni) 3151600100040 MONITOR (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3151600100041 MONIT-REF (,J.H.Baard+,B,BAARD,,,1989) 3151600100042 DECAY-MON (27-CO-58-G,70.82D,DG,811.79,.99448) Attenuation factor3151600100043 - 0.987. Data are taken 3151600100044 from J.K. Tuli, Nuclear Wallet Cards, BNL (1995) for 3151600100045 half-life and from R.B. Firestone and V. Shirley, Table3151600100046 of Isotopes (1996) for gamma-ray energy and emission 3151600100047 probability. Same sources were used for decay radiation3151600100048 parameters of all measured activities 3151600100049 CORRECTION Gamma-ray self-attenuation correction factors were 3151600100050 computed considering the foil samples as slabs and 3151600100051 using data from Nucl. Data Tables, Vol.7, Chap. 6 3151600100052 (1970) p. 565. 3151600100053 ERR-ANALYS (ERR-S)The statistical component of the uncertainty was3151600100054 obtained as weighted mean for a few measurements and 3151600100055 is given separately. 3151600100056 (ERR-T)The total uncertainty includes 3151600100057 the corresponding isotopic abundance uncertainty 3151600100058 (MONIT-ERR) 2.8% as uncertainty of the reference cross 3151600100059 section value, 3151600100060 (ERR-1) 2% - uncertainty in the detector absolute 3151600100061 efficiency determination, 3151600100062 (ERR-2,1.,2.) 1-2% other systematic uncertainties 3151600100063 (activation product decay constants, time 3151600100064 uncertainties and uncertainty of self-attenuation 3151600100065 correction. 3151600100066 STATUS (TABLE) Data taken from Table 2 of main reference. 3151600100067 HISTORY (20020213C) Compiled by VP 3151600100068 (20211004A) VS. REACTION corrected in 002. 3151600100069 ERR-ANALYS updated in 001. 3151600100070 ENDBIB 68 0 3151600100071 COMMON 4 3 3151600100072 EN-DUMMY MONIT MONIT-ERR ERR-1 3151600100073 MEV MB MB PER-CENT 3151600100074 1.5 111. 3. 2. 3151600100075 ENDCOMMON 3 0 3151600100076 ENDSUBENT 75 0 3151600199999 SUBENT 31516002 20020213 00003151600200001 BIB 5 12 3151600200002 REACTION (28-NI-60(N,P)27-CO-60-M,,SIG,,FIS) 3151600200003 DECAY-DATA (27-CO-60-M,10.476MIN,DG,58.603,.02036) Attenuation 3151600200004 factor - 0.846 3151600200005 SAMPLE Natural isotopic abundance of Ni-60 was taken as: 3151600200006 26.223+-0.008% 3151600200007 METHOD 6 samples were individually irradiated for 5 min under 3151600200008 1-mm-thick cadmium covers. After about 1 min decay, 2 3151600200009 10-min gamma spectra were measured for 58.6 keV peak. 3151600200010 At least 10 days later the measurements were done for 3151600200011 811.8 keV gamma-ray activity in the same geometry. 3151600200012 DETECTOR The gamma-ray efficiency for 58.6 keV peak was measured3151600200013 with Am-241 IAEA calibrated source 3151600200014 ENDBIB 12 0 3151600200015 NOCOMMON 0 0 3151600200016 DATA 3 1 3151600200017 DATA ERR-S ERR-T 3151600200018 MB MB MB 3151600200019 1.499 0.015 0.083 3151600200020 ENDDATA 3 0 3151600200021 ENDSUBENT 20 0 3151600299999 SUBENT 31516003 20020213 00003151600300001 BIB 4 10 3151600300002 REACTION (28-NI-61(N,P)27-CO-61,,SIG,,FIS) 3151600300003 DECAY-DATA (27-CO-61,1.650HR,DG,67.415,0.8467) Attenuation 3151600300004 factor - 0.892 3151600300005 SAMPLE Natural isotopic abundance of Ni-61 was taken as: 3151600300006 1.140+-0.001% 3151600300007 METHOD 6 samples were individually irradiated for 5 min under 3151600300008 1-mm-thick cadmium covers. After about 30 min decay, 3151600300009 gamma spectra were measured during 1 hour for 67.4 keV 3151600300010 peak. At least 10 min later the measurements were done 3151600300011 for 811.8 keV gamma-ray activity in the same geometry 3151600300012 ENDBIB 10 0 3151600300013 NOCOMMON 0 0 3151600300014 DATA 3 1 3151600300015 DATA ERR-S ERR-T 3151600300016 MB MB MB 3151600300017 1.632 0.012 0.096 3151600300018 ENDDATA 3 0 3151600300019 ENDSUBENT 18 0 3151600399999 SUBENT 31516004 20020213 00003151600400001 BIB 4 9 3151600400002 REACTION (28-NI-58(N,2N)28-NI-57,,SIG,,FIS) 3151600400003 DECAY-DATA (28-NI-57,35.60HR,DG,1377.,.817) 3151600400004 SAMPLE Natural isotopic abundance of Ni-58 was taken as: 3151600400005 68.077+-0.009% 3151600400006 METHOD 4 samples were individually irradiated for 5 to 10 min 3151600400007 under 1-mm-thick cadmium covers. After about 30 to 3151600400008 50 hr decay, gamma spectra were measured for about 3151600400009 30 hr. At least 10 min later the measurements were done3151600400010 for 811.8 keV gamma-ray activity in the same geometry 3151600400011 ENDBIB 9 0 3151600400012 NOCOMMON 0 0 3151600400013 DATA 3 1 3151600400014 DATA ERR-S ERR-T 3151600400015 MB MB MB 3151600400016 0.00472 0.00012 0.00026 3151600400017 ENDDATA 3 0 3151600400018 ENDSUBENT 17 0 3151600499999 SUBENT 31516005 20211005 32023151600500001 BIB 5 12 3151600500002 REACTION (28-NI-58(N,X)27-CO-57,,SIG,,FIS) 3151600500003 DECAY-DATA (27-CO-57,271.79D,DG,122.06,.856) 3151600500004 SAMPLE Natural isotopic abundance of Ni-58 was taken as: 3151600500005 68.077+-0.009% 3151600500006 METHOD 4 samples were individually irradiated for 5 to 10 min 3151600500007 and fifth sample was irradiated at the same position 3151600500008 for 10 hr. After a 300-day decay all five samples were 3151600500009 counted from 50 to 100 hr. Correction on contribution 3151600500010 from Ni-58(n,2n)Ni-57 -> beta+ decay ->Co-57 branch 3151600500011 was introduced using (n,2n) cross section of this work 3151600500012 HISTORY (20211004A) VS. REACTION corrected c.f. Memos CP-D/09993151600500013 and CP-D/0954. 3151600500014 ENDBIB 12 0 3151600500015 NOCOMMON 0 0 3151600500016 DATA 3 1 3151600500017 DATA ERR-S ERR-T 3151600500018 MB MB MB 3151600500019 0.2746 0.0076 0.015 3151600500020 ENDDATA 3 0 3151600500021 ENDSUBENT 20 0 3151600599999 SUBENT 31516006 20020213 00003151600600001 BIB 4 16 3151600600002 REACTION (28-NI-58(N,P)27-CO-58-G,,SIG,,FIS) 3151600600003 DECAY-DATA (27-CO-58-G,70.82D,DG,811.79,.9948) 3151600600004 SAMPLE Natural isotopic abundance of Ni-58 was taken as: 3151600600005 68.077+-0.009% 3151600600006 METHOD 3 samples were individually irradiated under 1 mm-thick3151600600007 cadmium covers for 20 min. After about 1 hr decay, a 3151600600008 series of 12 20-min spectra were taken in a period of 3151600600009 24 hr; between about 50 and 100 hr decay another eight 3151600600010 1 hr spectra were taken and last spectrum was measured 3151600600011 after an 8-day decay. Last spectrum was used as 3151600600012 for Ni-58(n,p)Co-58m+g reaction. From equation of decay3151600600013 and peak area of 811.8 keV gamma ray measured in these 3151600600014 spectra the cross sections with independent yield of 3151600600015 Co-58-m and Co-58-g can be determined as independent 3151600600016 From sample mass and purity, fast neutron flux, 3151600600017 gamma-ray yield, and sample-detector counting geometry 3151600600018 ENDBIB 16 0 3151600600019 NOCOMMON 0 0 3151600600020 DATA 3 1 3151600600021 DATA ERR-S ERR-T 3151600600022 MB MB MB 3151600600023 74.77 0.92 2.3 3151600600024 ENDDATA 3 0 3151600600025 ENDSUBENT 24 0 3151600699999 SUBENT 31516007 20020213 00003151600700001 BIB 4 17 3151600700002 REACTION (28-NI-58(N,P)27-CO-58-M,,SIG,,FIS) 3151600700003 DECAY-DATA (27-CO-58-M,9.15HR) 3151600700004 (27-CO-58-G,70.82D,DG,811.79,.9948) 3151600700005 SAMPLE Natural isotopic abundance of Ni-58 was taken as: 3151600700006 68.077+-0.009% 3151600700007 METHOD 3 samples were individually irradiated under 1 mm-thick3151600700008 cadmium covers for 20 min. After about 1 hr decay, a 3151600700009 series of 12 20-min spectra were taken in a period of 3151600700010 24 hr; between about 50 and 100 hr decay another eight 3151600700011 1 hr spectra were taken and last spectrum was measured 3151600700012 after an 8-day decay. Last spectrum was used as 3151600700013 for Ni-58(n,p)Co-58m+g reaction. From equation of decay3151600700014 and peak area of 811.8 keV gamma ray measured in these 3151600700015 spectra the cross sections with independent yield of 3151600700016 Co-58-m and Co-58-g can be determined as independent 3151600700017 From sample mass and purity, fast neutron flux, 3151600700018 gamma-ray yield, and sample-detector counting geometry 3151600700019 ENDBIB 17 0 3151600700020 NOCOMMON 0 0 3151600700021 DATA 3 1 3151600700022 DATA ERR-S ERR-T 3151600700023 MB MB MB 3151600700024 36.55 0.58 1.2 3151600700025 ENDDATA 3 0 3151600700026 ENDSUBENT 25 0 3151600799999 ENDENTRY 7 0 3151699999999