ENTRY 23301 20191119 22832330100000001 SUBENT 23301001 20191119 22832330100100001 BIB 11 70 2330100100002 AUTHOR (N.Jovancevic, L.Daraban, H.Stroh, S.Oberstedt,M.Hult, 2330100100003 C.Bonaldi, W.Geerts, F.-J.Hambsch,G.Lutter,G.Marissens,2330100100004 M.Vidali) 2330100100005 TITLE The neutron cross-section functions for the reactions 2330100100006 187Re(n,a)184Ta, 187Re(n,2n)186Re and 185Re(n,2n)184Re 2330100100007 in the energy range 13.08 - 19.5 MeV. 2330100100008 REFERENCE (J,EPJ/A,52,148,2016) 2330100100009 #doi:10.1140/epja/i2016-16148-4 2330100100010 (J,EPJ/CS,146,11025,2017) - same data + data for 2330100100011 187Re(n,p)187W and 185Re(n,3n)183Re 2330100100012 INSTITUTE (2ZZZGEL) 2330100100013 (3SRBSRB) Department of Physics, Faculty of Sciences, 2330100100014 University of Novi Sad, Trg Dositeja Obradovica 3, 2330100100015 21000 Novi Sad, Serbia . N.Jovancevic . 2330100100016 FACILITY (VDG,2ZZZGEL) 2330100100017 INC-SOURCE (D-T) Ti-3H target of 2.293mg cm-2. The 3H/Ti ratio was2330100100018 calculated to be 1.4 at the start of the irradiation. 2330100100019 SAMPLE Pure (99.9%) natural Re metal disks of identical shape2330100100020 with a diameter of 20mm, 5mm thick and of mass (gram): 2330100100021 1) 28.93180+-0.00005, 2) 30.13020+-0.00005, 2330100100022 3) 29.83400+-0.00005, 4) 29.77400+-0.00005, 2330100100023 5) 30.25310+-0.00005, 6) 29.01820+-0.00005, 2330100100024 7) 30.23730+-0.00005. 2330100100025 U-238 mass 0.861+-0.016 mg . 2330100100026 METHOD (ACTIV,GSPEC) Irradiation of several (6 in this study) 2330100100027 metal disks in different wide-energy neutron beams. 2330100100028 One further disk was irradiated at a well-defined 2330100100029 incident neutron energy and measured - for normalizing.2330100100030 Each disk was irradiated at one neutron energy and in 2330100100031 an interval from 0deg to 80deg relative to the 2330100100032 direction of the beam at 41 different positions, in 2330100100033 steps of 2deg. 2330100100034 Irradiation at 0deg: 2330100100035 Disc # Eion,MeV En,MeV Irradiation time(sec)2330100100036 1 3.300+-0.011 19.78+-0.20 86921+-10 2330100100037 2 2.500+-0.011 18.71+-0.20 248402+-10 2330100100038 3 2.000+-0.011 18.10+-0.28 157632+-10 2330100100039 4(norm) 2.000+-0.011 18.10+-0.28 166564+-10 2330100100040 5 1.500+-0.011 17.16+-0.30 231958+-10 2330100100041 6 1.000+-0.011 15.97+-0.82 243608+-10 2330100100042 7 0.800+-0.011 15.26+-1.31 144831+-10 2330100100043 Distance sample - neutron target was 20 cm . 2330100100044 DETECTOR (BF3,IOCH,IOCH) 2330100100045 During irradiation, the neutron fluence rate was 2330100100046 monitored by a BF3 long counter and an ionization 2330100100047 chambers loaded with a 235U and 238U targets. 2330100100048 The 238U chamber was placed at the same position as 2330100100049 the Re disk and measurement was done before each disk 2330100100050 irradiation. 2330100100051 The 235U chamber was calibrated against the 238U 2330100100052 chamber and used as neutron fluence monitor during 2330100100053 the Re disk activation; was placed 111 cm away from 2330100100054 the neutron-producing target and at 50DEG relative to 2330100100055 the ion beam. 2330100100056 (HPGE) Low-background HPGe-detectors were used for 2330100100057 high-resolution gamma-ray spectroscopy: 2330100100058 - coaxial HPGe-detector with a 40% relative efficiency 2330100100059 at first measurement of each sample started after 2330100100060 around 20 min cooling time; 2330100100061 - planar point contact HPGe-detector (so-called BEGe) 2330100100062 with 50% relative efficiency at subsequent measurements2330100100063 after 2 days in the ultra-low background underground 2330100100064 laboratory HADES; 2330100100065 ANALYSIS (UNFLD) The neutron cross-sections were calculated 2330100100066 using an unfolding procedure, where the known spectra 2330100100067 of the neutron beams and the activity of the 2330100100068 radionuclides are input parameters. 2330100100069 HISTORY (20160810C) M.M. 2330100100070 (20191119A) SD: Ref. EPJ/CS,146,11025,2017 added. 2330100100071 Subents 008, 009 added. PART-DET deleted. 2330100100072 ENDBIB 70 0 2330100100073 NOCOMMON 0 0 2330100100074 ENDSUBENT 73 0 2330100199999 SUBENT 23301002 20160810 22542330100200001 BIB 8 20 2330100200002 REACTION (75-RE-187(N,2N)75-RE-186-G,(M),SIG) 2330100200003 DECAY-DATA (75-RE-186-G,3.7186D,DG,137.2,0.094) 2330100200004 3.7186+-0.0005 d from BNL data base (comment of 2330100200005 S.Oberstedt) 2330100200006 MONITOR (92-U-238(N,F),,SIG) For average neutron fluence rate. 2330100200007 From ENDF data base. 2330100200008 ANALYSIS Cross section was determined as: 2330100200009 Ak/F1 , where Ak - measured induced activity, 2330100200010 F1 - average fluence rate corrected for variation in 2330100200011 the ion beam current; measured with two ionization 2330100200012 chambers with 238U and 235U targets. 2330100200013 Contribution of long-lived isomer Re-186-m was 2330100200014 considered as negligible (comment of S.Obertsedt) 2330100200015 COMMENT Of author. CS was not corrected for isomeric transition2330100200016 contribution (N.Jovancevic, 20017-02-03, via N.Otsuka).2330100200017 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100200018 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 2330100200019 article. 2330100200020 STATUS (TABLE) Table 4 (data), Table 3 (decay data) of 2330100200021 J,EPJ/A,52,148,2016 . 2330100200022 ENDBIB 20 0 2330100200023 COMMON 2 3 2330100200024 MONIT MONIT-ERR 2330100200025 B B 2330100200026 1.315 0.013 2330100200027 ENDCOMMON 3 0 2330100200028 DATA 6 1 2330100200029 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100200030 MEV MEV B B SEE TEXT SEE TEXT 2330100200031 18.10 0.28 0.713 0.023 6700. 200. 2330100200032 ENDDATA 3 0 2330100200033 ENDSUBENT 32 0 2330100299999 SUBENT 23301003 20160810 22542330100300001 BIB 7 15 2330100300002 REACTION (75-RE-187(N,A)73-TA-184,,SIG) 2330100300003 DECAY-DATA (73-TA-184,8.7HR,DG,414.0,0.739) 2330100300004 8.7+-0.1 hr from BNL data base (comment of S.Oberstedt)2330100300005 MONITOR (92-U-238(N,F),,SIG) For average neutron fluence rate. 2330100300006 From ENDF data base. 2330100300007 ANALYSIS Cross section was determined as: 2330100300008 Ak/F1 , where Ak - measured induced activity, 2330100300009 F1 - average fluence rate corrected for variation in 2330100300010 the ion beam current; measured with two ionization 2330100300011 chambers with 238U and 235U targets. 2330100300012 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100300013 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 2330100300014 article. 2330100300015 STATUS (TABLE) Table 4 (data), Table 3 (decay data) of 2330100300016 J,EPJ/A,52,148,2016 . 2330100300017 ENDBIB 15 0 2330100300018 COMMON 2 3 2330100300019 MONIT MONIT-ERR 2330100300020 B B 2330100300021 1.315 0.013 2330100300022 ENDCOMMON 3 0 2330100300023 DATA 6 1 2330100300024 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100300025 MEV MEV B B SEE TEXT SEE TEXT 2330100300026 18.10 0.28 0.00152 0.00005 24600. 700. 2330100300027 ENDDATA 3 0 2330100300028 ENDSUBENT 27 0 2330100399999 SUBENT 23301004 20160810 22542330100400001 BIB 8 19 2330100400002 REACTION (75-RE-185(N,2N)75-RE-184-G,(M),SIG) 2330100400003 DECAY-DATA (75-RE-184-G,35.4D,DG,903.,0.379) 2330100400004 35.4+-0.7 d from BNL data base (comment of S.Oberstedt)2330100400005 MONITOR (92-U-238(N,F),,SIG) For average neutron fluence rate. 2330100400006 From ENDF data base. 2330100400007 ANALYSIS Cross section was determined as: 2330100400008 Ak/F1 , where Ak - measured induced activity, 2330100400009 F1 - average fluence rate corrected for variation in 2330100400010 the ion beam current; measured with two ionization 2330100400011 chambers with 238U and 235U targets. 2330100400012 Contribution of long-lived isomer Re-184-m was 2330100400013 considered as negligible ( comment of S.Obertsedt) 2330100400014 COMMENT Of author. CS was not corrected for isomeric transition2330100400015 contribution (N.Jovancevic, 20017-02-03, via N.Otsuka).2330100400016 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100400017 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 2330100400018 article. 2330100400019 STATUS (TABLE) Table 4 (data), Table 3 (decay data) of 2330100400020 J,EPJ/A,52,148,2016 . 2330100400021 ENDBIB 19 0 2330100400022 COMMON 2 3 2330100400023 MONIT MONIT-ERR 2330100400024 B B 2330100400025 1.315 0.013 2330100400026 ENDCOMMON 3 0 2330100400027 DATA 6 1 2330100400028 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100400029 MEV MEV B B SEE TEXT SEE TEXT 2330100400030 18.10 0.28 0.904 0.030 811. 24. 2330100400031 ENDDATA 3 0 2330100400032 ENDSUBENT 31 0 2330100499999 SUBENT 23301005 20160810 22542330100500001 BIB 10 33 2330100500002 REACTION (75-RE-187(N,2N)75-RE-186-G,(M),SIG) 2330100500003 DECAY-DATA (75-RE-186-G,,DG,137.2,0.094) 2330100500004 MONITOR (75-RE-187(N,2N)75-RE-186,,SIG) CS measured at 18.1 MeV2330100500005 MONIT-REF (23301002,N.Jovancevic+,J,EPJ/A,52,148,2016) 2330100500006 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100500007 ANALYSIS The average cross-section was calculated for each 2330100500008 irradiation in different neutron fields as : 2330100500009 k = SUM(Fki * Ei)/SUM(Fki). 2330100500014 A linear interpolation of the energy dependence of the 2330100500015 obtained cross-section values on energy k was used. 2330100500016 The obtained interpolated functions are normalized to 2330100500017 the cross-section values determined for the 18.1MeV 2330100500018 neutron energy. 2330100500019 COMMENT Of author. CS was not corrected for isomeric transition2330100500020 contribution (N.Jovancevic, 20017-02-03, via N.Otsuka).2330100500021 FLAG (1.) Disc 1 2330100500022 (2.) Disc 2 2330100500023 (3.) Disc 3 2330100500024 (5.) Disc 5 2330100500025 (6.) Disc 6 2330100500026 (7.) Disc 7 2330100500027 ERR-ANALYS (DATA-ERR) Include uncertainties coming from 2330100500028 - the calculation of the neutron fields, 2330100500029 - the measurement of the induced gamma ray activity, 2330100500030 - the measurements of the distance between the 2330100500031 neutron-producing target and the irradiated disks, 2330100500032 - the weighting of the disks, 2330100500033 - the measurements of the beam current. 2330100500034 STATUS (TABLE) Table 5 of J,EPJ/A,52,148,2016 . 2330100500035 ENDBIB 33 0 2330100500036 COMMON 1 3 2330100500037 EN-NRM 2330100500038 MEV 2330100500039 18.1 2330100500040 ENDCOMMON 3 0 2330100500041 DATA 7 6 2330100500042 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100500043 FLAG 2330100500044 MEV MEV B B SEE TEXT SEE TEXT 2330100500045 NO-DIM 2330100500046 18.3 1.2 0.71 0.04 4400. 220. 2330100500047 1. 2330100500048 17.3 1.0 0.82 0.04 11100. 600. 2330100500049 2. 2330100500050 16.8 0.9 0.69 0.04 6000. 300. 2330100500051 3. 2330100500052 16.1 0.7 0.95 0.05 14200. 700. 2330100500053 5. 2330100500054 15.3 0.5 1.39 0.07 17700. 900. 2330100500055 6. 2330100500056 14.7 0.4 1.14 0.06 19900. 1000. 2330100500057 7. 2330100500058 ENDDATA 16 0 2330100500059 ENDSUBENT 58 0 2330100599999 SUBENT 23301006 20160810 22542330100600001 BIB 9 31 2330100600002 REACTION (75-RE-187(N,A)73-TA-184,,SIG) 2330100600003 DECAY-DATA (73-TA-184,,DG,903.,0.379) 2330100600004 MONITOR (75-RE-187(N,A)73-TA-184,,SIG) CS measured at 18.1 MeV 2330100600005 MONIT-REF (23301003,N.Jovancevic+,J,EPJ/A,52,148,2016) 2330100600006 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100600007 ANALYSIS The average cross-section was calculated for each 2330100600008 irradiation in different neutron fields as : 2330100600009 k = SUM(Fki * Ei)/SUM(Fki). 2330100600014 A linear interpolation of the energy dependence of the 2330100600015 obtained cross-section values on energy k was used. 2330100600016 The obtained interpolated functions are normalized to 2330100600017 the cross-section values determined for the 18.1MeV 2330100600018 neutron energy. 2330100600019 FLAG (1.) Disc 1 2330100600020 (2.) Disc 2 2330100600021 (3.) Disc 3 2330100600022 (5.) Disc 5 2330100600023 (6.) Disc 6 2330100600024 (7.) Disc 7 2330100600025 ERR-ANALYS (DATA-ERR) Include uncertainties coming from 2330100600026 - the calculation of the neutron fields, 2330100600027 - the measurement of the induced gamma ray activity, 2330100600028 - the measurements of the distance between the 2330100600029 neutron-producing target and the irradiated disks, 2330100600030 - the weighting of the disks, 2330100600031 - the measurements of the beam current. 2330100600032 STATUS (TABLE) Table 5 of J,EPJ/A,52,148,2016 . 2330100600033 ENDBIB 31 0 2330100600034 COMMON 1 3 2330100600035 EN-NRM 2330100600036 MEV 2330100600037 18.1 2330100600038 ENDCOMMON 3 0 2330100600039 DATA 7 6 2330100600040 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100600041 FLAG 2330100600042 MEV MEV B B SEE TEXT SEE TEXT 2330100600043 NO-DIM 2330100600044 18.3 1.2 0.00152 0.00008 22200. 1100. 2330100600045 1. 2330100600046 17.3 1.0 0.00099 0.00005 27100. 1400. 2330100600047 2. 2330100600048 16.8 0.9 0.00106 0.00006 18000. 900. 2330100600049 3. 2330100600050 16.1 0.7 0.00107 0.00006 34400. 1700. 2330100600051 5. 2330100600052 15.3 0.6 0.00089 0.00005 41900. 2100. 2330100600053 6. 2330100600054 14.8 0.5 0.00053 0.00003 68000. 3000. 2330100600055 7. 2330100600056 ENDDATA 16 0 2330100600057 ENDSUBENT 56 0 2330100699999 SUBENT 23301007 20160810 22542330100700001 BIB 10 33 2330100700002 REACTION (75-RE-185(N,2N)75-RE-184-G,(M),SIG) 2330100700003 DECAY-DATA (75-RE-184-G,,DG,903.,0.379) 2330100700004 MONITOR (75-RE-185(N,2N)75-RE-184,,SIG) CS measured at 18.1 MeV2330100700005 MONIT-REF (23301004,N.Jovancevic+,J,EPJ/A,52,148,2016) 2330100700006 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100700007 ANALYSIS The average cross-section was calculated for each 2330100700008 irradiation in different neutron fields as : 2330100700009 k = SUM(Fki * Ei)/SUM(Fki). 2330100700014 A linear interpolation of the energy dependence of the 2330100700015 obtained cross-section values on energy k was used. 2330100700016 The obtained interpolated functions are normalized to 2330100700017 the cross-section values determined for the 18.1MeV 2330100700018 neutron energy. 2330100700019 FLAG (1.) Disc 1 2330100700020 (2.) Disc 2 2330100700021 (3.) Disc 3 2330100700022 (5.) Disc 5 2330100700023 (6.) Disc 6 2330100700024 (7.) Disc 7 2330100700025 COMMENT Of author. CS was not corrected for isomeric transition2330100700026 contribution (N.Jovancevic, 20017-02-03, via N.Otsuka).2330100700027 ERR-ANALYS (DATA-ERR) Include uncertainties coming from 2330100700028 - the calculation of the neutron fields, 2330100700029 - the measurement of the induced gamma ray activity, 2330100700030 - the measurements of the distance between the 2330100700031 neutron-producing target and the irradiated disks, 2330100700032 - the weighting of the disks, 2330100700033 - the measurements of the beam current. 2330100700034 STATUS (TABLE) Table 5 of J,EPJ/A,52,148,2016 . 2330100700035 ENDBIB 33 0 2330100700036 COMMON 1 3 2330100700037 EN-NRM 2330100700038 MEV 2330100700039 18.1 2330100700040 ENDCOMMON 3 0 2330100700041 DATA 7 6 2330100700042 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100700043 FLAG 2330100700044 MEV MEV B B SEE TEXT SEE TEXT 2330100700045 NO-DIM 2330100700046 18.3 1.2 0.90 0.05 505. 25. 2330100700047 1. 2330100700048 17.3 1.0 1.24 0.06 1460. 70. 2330100700049 2. 2330100700050 16.8 0.9 1.26 0.07 740. 40. 2330100700051 3. 2330100700052 16.1 0.7 1.67 0.09 1850. 90. 2330100700053 5. 2330100700054 15.3 0.6 2.17 0.01 2300. 110. 2330100700055 6. 2330100700056 14.7 0.4 1.90 0.10 2400. 120. 2330100700057 7. 2330100700058 ENDDATA 16 0 2330100700059 ENDSUBENT 58 0 2330100799999 SUBENT 23301008 20191119 22832330100800001 BIB 8 14 2330100800002 REACTION (75-RE-185(N,3N)75-RE-183,,SIG) 2330100800003 DECAY-DATA (75-RE-183,,DG,162.3,0.22) 2330100800004 MONITOR (92-U-238(N,F),,SIG) For average neutron fluence rate. 2330100800005 From ENDF data base. 2330100800006 ANALYSIS Cross section was determined as: 2330100800007 Ak/F1 , where Ak - measured induced activity, 2330100800008 F1 - average fluence rate corrected for variation in 2330100800009 the ion beam current; measured with two ionization 2330100800010 chambers with 238U and 235U targets. 2330100800011 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100800012 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 2330100800013 article. 2330100800014 STATUS (TABLE) Table 3 from EPJ Web of Conf.,146(2017)11025 2330100800015 HISTORY (20191119C) SD 2330100800016 ENDBIB 14 0 2330100800017 COMMON 2 3 2330100800018 MONIT MONIT-ERR 2330100800019 B B 2330100800020 1.315 0.013 2330100800021 ENDCOMMON 3 0 2330100800022 DATA 6 1 2330100800023 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100800024 MEV MEV B B SEE TEXT SEE TEXT 2330100800025 18.10 0.28 0.845 0.029 17200. 500. 2330100800026 ENDDATA 3 0 2330100800027 ENDSUBENT 26 0 2330100899999 SUBENT 23301009 20191119 22832330100900001 BIB 8 14 2330100900002 REACTION (75-RE-187(N,P)74-W-187,,SIG) 2330100900003 DECAY-DATA (74-W-187,,DG,618.3,0.076) 2330100900004 MONITOR (92-U-238(N,F),,SIG) For average neutron fluence rate. 2330100900005 From ENDF data base. 2330100900006 ANALYSIS Cross section was determined as: 2330100900007 Ak/F1 , where Ak - measured induced activity, 2330100900008 F1 - average fluence rate corrected for variation in 2330100900009 the ion beam current; measured with two ionization 2330100900010 chambers with 238U and 235U targets. 2330100900011 MISC-COL (MISC) Average neutron fluence rate, 1/(cm2*sec) 2330100900012 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 2330100900013 article. 2330100900014 STATUS (TABLE) Table 3 from EPJ Web of Conf.,146(2017)11025 2330100900015 HISTORY (20191119C) SD 2330100900016 ENDBIB 14 0 2330100900017 COMMON 2 3 2330100900018 MONIT MONIT-ERR 2330100900019 B B 2330100900020 1.315 0.013 2330100900021 ENDCOMMON 3 0 2330100900022 DATA 6 1 2330100900023 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2330100900024 MEV MEV B B SEE TEXT SEE TEXT 2330100900025 18.10 0.28 0.00480 0.00017 377. 11. 2330100900026 ENDDATA 3 0 2330100900027 ENDSUBENT 26 0 2330100999999 ENDENTRY 9 0 2330199999999