ENTRY 30364 20100305 31443036400000001 SUBENT 30364001 20100305 31443036400100001 BIB 17 74 3036400100002 INSTITUTE (3SLNIJS) 3036400100003 REFERENCE (R,INDC(YUG)-5,197701) Report to IAEA. 3036400100004 (J,NIM,44,292,196610) Improved spectrometer described. 3036400100005 (R,NIJS-R-470,196511) Same as Nucl.Ins. 3036400100006 Methods,44(1966)292 3036400100007 REL-REF (M,,F.Cvelbar+,J,NP/A,130,401,1969)descr.method,no data3036400100008 (M,,,R,NIJS-R-502,1967) Descr.method,no data 3036400100009 AUTHOR (M.Budnar,F.Cvelbar,A.Likar,R.Martincic,M.Potokar, 3036400100010 V.Ivkovic) 3036400100011 TITLE -Gamma-ray spectra and (n,gamma) cross-sections at 3036400100012 14 MeV for Sc, Y, Pr and Ho.- 3036400100013 EXP-YEAR (1975) Measurements from 1974 to 1976. 3036400100014 FACILITY (CCW) Cockcroft-Walton accelerator, energy of incident 3036400100015 deuteron is 100 keV. 3036400100016 INC-SOURCE (D-T) T(d,n)He-4 reaction. 3036400100017 INC-SPECT The ''energy-spread'' is 1.35 MeV,that is +- 0.675 MeV.3036400100018 neutron flux is ~10**8 (1+-0.1) n/sec 3036400100019 SAMPLE Mono isotopic composition, targets are spheres 3036400100020 (hemispheres) with diameter 5 to 6 cm placed close to 3036400100021 the tritium target. Therefore the neutron energy is 3036400100022 spread over a range from 13.5 to 14.7 MeV. Due to 3036400100023 this geometry the spectra obtained are integrated 3036400100024 over a solid angle of 2pi (or 4Pi for hemi- spheres). 3036400100025 METHOD Gamma spectra were measured with the telescopic 3036400100026 scintillation pair spectrometer. 3036400100027 Recoil proton spectrometer was used for neutron 3036400100028 monitoring. 3036400100029 DETECTOR (BPAIR) Scintillation pair spectrometer which 3036400100030 resolution has been measured to be 12.5, 9.5 and 8.0 3036400100031 per cent for gammas of energies 12.1,16.5 and 20.4 MeV,3036400100032 respectively. 3036400100033 Efficiencies for these gamma energies have been 3036400100034 measured to be 0.45,0.55 and 0.56 percent,respectively.3036400100035 (CSICR) Recoil proton spectrometer using a CsI(Tl) 3036400100036 crystal for neutron-flux monitoring. The accuracy of 3036400100037 the determination of the neutron flux was +- 6%. 3036400100038 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 3036400100039 For neutron-flux determination. 3036400100040 CORRECTION Spectra were corrected for 3036400100041 .background, 3036400100042 .the spectrometer response function, 3036400100043 .the gammas created and absorbed in the sample, 3036400100044 .absorption of gammas in the paraffin-collimator, and 3036400100045 .neutron nonelastic process in the target. 3036400100046 ERR-ANALYS (ERR-T) The overall error includes the uncertainties: 3036400100047 . due to statistical errors, 3036400100048 . on the background correction, 3036400100049 (ERR-1,1.,7.) 7% for spheres, 1% for hemisphers, 3036400100050 . due to spectrometer response function which 3036400100051 enlarges statistical error by a factor of 1.8, 3036400100052 . on the energy scale 3036400100053 2% at 14 MeV, 3% at 22 MeV, 3036400100054 (ERR-2) on the spectrometer efficiency of 11%, 3036400100055 (ERR-3) on the correction for absorption of gammas, 1%,3036400100056 (ERR-4) on the correction for nonelastic processes in 3036400100057 the target, 2%, 3036400100058 (ERR-5) on the neutron flux, 6%, 3036400100059 (ERR-6) on the anisotropy of gammas, 3%, 3036400100060 (ERR-7) due to the assumption of equal solid angle for 3036400100061 the whole sample, 1%. 3036400100062 The resulting error for the cross-sections 3036400100063 was about 15%. 3036400100064 The energy resolution of gamma ray has been determined3036400100065 by the energy width of the spectrometer response 3036400100066 function (1.65+-0.05) and by the energy spread of the 3036400100067 neutron beam (1.35 MeV). The resulting resolution are 3036400100068 14% at 15 MeV, and 10% at 21 MeV. 3036400100069 STATUS (SPSDD,30532001) 3036400100070 - All subentries superseded by Entry 50532 - 3036400100071 earlier status entry was = approved by budnar(76/12/01)3036400100072 HISTORY (19761201C) Compiled by Budnar, minor amendments by NDS3036400100073 (19800303A) OS. Status changed to 'superseded' 3036400100074 (20100305A) SD:Updated to new date formats,lower case. 3036400100075 Cosmetic changes 3036400100076 ENDBIB 74 0 3036400100077 COMMON 8 6 3036400100078 EN EN-RSL ERR-2 ERR-3 ERR-4 ERR-5 3036400100079 ERR-6 ERR-7 3036400100080 MEV MEV PER-CENT PER-CENT PER-CENT PER-CENT 3036400100081 PER-CENT PER-CENT 3036400100082 1.4100E+01 6.7500E-01 11. 1. 2. 6. 3036400100083 3. 1. 3036400100084 ENDCOMMON 6 0 3036400100085 ENDSUBENT 84 0 3036400199999 SUBENT 30364002 20100305 31443036400200001 BIB 3 10 3036400200002 REACTION (21-SC-45(N,G)21-SC-46,,DE) 3036400200003 ANALYSIS The differential cross section for radiative capture 3036400200004 of 14.1 MeV neutron can be obtained from real gamma 3036400200005 spectrum 'S' and the effective number of neutrons in 3036400200006 the sample 'I', if also the geometry of experiment 3036400200007 '4Pi/omega' and the number of sample nuclei in a unit 3036400200008 volume 'n' are taken into consideration. 3036400200009 D-sig/d-E(g) = (4Pi/omega)*(1/(n*I*r))*S(micro-B/.5MeV)3036400200010 where 'r' stands for the effective sample radius. 3036400200011 STATUS (SPSDD,30532015) 3036400200012 ENDBIB 10 0 3036400200013 NOCOMMON 0 0 3036400200014 NODATA 0 0 3036400200015 ENDSUBENT 14 0 3036400299999 SUBENT 30364003 20100305 31443036400300001 BIB 3 9 3036400300002 REACTION (21-SC-45(N,G)21-SC-46,,SIG) 3036400300003 ANALYSIS The cross-sections are obtained by integration of the 3036400300004 fully corrected gamma spectrum over the excitation 3036400300005 energy interval up to the binding energy of last 3036400300006 neutron in the final nucleus. 3036400300007 STATUS (SPSDD,30532014) 3036400300008 (DEP,30364002) Dependent data on sub-entry .002, see 3036400300009 'analysis'. 3036400300010 (TABLE) data from Table 4 of INDC-(YUG)-5/L. 3036400300011 ENDBIB 9 0 3036400300012 NOCOMMON 0 0 3036400300013 NODATA 0 0 3036400300014 ENDSUBENT 13 0 3036400399999 SUBENT 30364004 20100305 31443036400400001 BIB 3 10 3036400400002 REACTION (39-Y-89(N,G)39-Y-90,,DE) 3036400400003 ANALYSIS The differential cross section for radiative capture 3036400400004 of 14.1 MeV neutron can be obtained from real gamma 3036400400005 spectrum 'S' and the effective number of neutrons in 3036400400006 the sample 'I', if also the geometry of experiment 3036400400007 '4pi/omega' and the number of sample nuclei in a unit 3036400400008 volume 'n' are taken into consideration. 3036400400009 D-sig/d-E(g) = (4Pi/omega)*(1/(n*I*r))*S(micro-B/.5MeV)3036400400010 where 'r' stands for the effective sample radius. 3036400400011 STATUS (SPSDD,30532035) 3036400400012 ENDBIB 10 0 3036400400013 NOCOMMON 0 0 3036400400014 NODATA 0 0 3036400400015 ENDSUBENT 14 0 3036400499999 SUBENT 30364005 20100305 31443036400500001 BIB 3 9 3036400500002 REACTION (39-Y-89(N,G)39-Y-90,,SIG) 3036400500003 ANALYSIS The cross-sections are obtained by integration of the 3036400500004 fully corrected gamma spectrum over the excitation 3036400500005 energy interval up to the binding energy of last 3036400500006 neutron in the final nucleus. 3036400500007 STATUS (SPSDD,30532034) 3036400500008 (DEP,30364004) Dependent data on sub-entry .004, see 3036400500009 'analysis'. 3036400500010 (TABLE) data from Table 4 of INDC-(YUG)-5/L. 3036400500011 ENDBIB 9 0 3036400500012 NOCOMMON 0 0 3036400500013 NODATA 0 0 3036400500014 ENDSUBENT 13 0 3036400599999 SUBENT 30364006 20100305 31443036400600001 BIB 3 10 3036400600002 REACTION (59-PR-141(N,G)59-PR-142,,DE) 3036400600003 ANALYSIS The differential cross section for radiative capture 3036400600004 of 14.1 MeV neutron can Be obtained from real gamma 3036400600005 spectrum 'S' and the effective number of neutrons in 3036400600006 the sample 'I', if also the geometry of experiment 3036400600007 '4pi/omega' and the number of sample nuclei in a unit 3036400600008 volume 'n' are taken into consideration. 3036400600009 D-sig/d-E(g) = (4pi/omega)*(1/(n*I*r))*S(micro-B/.5MeV)3036400600010 where 'r' stands for the effective sample radius. 3036400600011 STATUS (SPSDD,30532045) 3036400600012 ENDBIB 10 0 3036400600013 NOCOMMON 0 0 3036400600014 NODATA 0 0 3036400600015 ENDSUBENT 14 0 3036400699999 SUBENT 30364007 20100305 31443036400700001 BIB 3 9 3036400700002 REACTION (59-PR-141(N,G)59-PR-142,,SIG) 3036400700003 ANALYSIS The cross-sections are obtained by integration of the 3036400700004 fully corrected gamma spectrum over the excitation 3036400700005 energy interval up to the binding energy of last 3036400700006 neutron in the final nucleus. 3036400700007 STATUS (SPSDD,30532044) 3036400700008 (DEP,30364006) Dependent data on sub-entry .006, see 3036400700009 'analysis'. 3036400700010 (TABLE) data from Table 4 of INDC-(YUG)-5/L. 3036400700011 ENDBIB 9 0 3036400700012 NOCOMMON 0 0 3036400700013 NODATA 0 0 3036400700014 ENDSUBENT 13 0 3036400799999 SUBENT 30364008 20100305 31443036400800001 BIB 3 10 3036400800002 REACTION (67-HO-165(N,G)67-HO-166,,DE) 3036400800003 ANALYSIS The differential cross section for radiative capture 3036400800004 of 14.1 MeV neutron can be obtained from real gamma 3036400800005 spectrum 'S' and the effective number of neutrons in 3036400800006 the sample 'I', if also the geometry of experiment 3036400800007 '4pi/omega' and the number of sample nuclei in a unit 3036400800008 volume 'n' are taken into consideration. 3036400800009 D-sig/d-E(g) = (4pi/omega)*(1/(n*I*r))*S(micro-B/.5MeV)3036400800010 where 'r' stands for the effective sample radius. 3036400800011 STATUS (SPSDD,30532047) 3036400800012 ENDBIB 10 0 3036400800013 NOCOMMON 0 0 3036400800014 NODATA 0 0 3036400800015 ENDSUBENT 14 0 3036400899999 SUBENT 30364009 20100305 31443036400900001 BIB 3 9 3036400900002 REACTION (67-HO-165(N,G)67-HO-166,,SIG) 3036400900003 ANALYSIS The cross-sections are obtained by integration of the 3036400900004 fully corrected gamma spectrum over the excitation 3036400900005 energy interval up to the binding energy of last 3036400900006 neutron in the final nucleus. 3036400900007 STATUS (SPSDD,30532046) 3036400900008 (DEP,30364008) Dependent data on sub-entry .008, see 3036400900009 'analysis'. 3036400900010 (TABLE) data from Table 4 of INDC-(YUG)-5/L. 3036400900011 ENDBIB 9 0 3036400900012 NOCOMMON 0 0 3036400900013 NODATA 0 0 3036400900014 ENDSUBENT 13 0 3036400999999 ENDENTRY 9 0 3036499999999