ENTRY 22247 20200808 22902224700000001 SUBENT 22247001 20200808 22902224700100001 BIB 15 92 2224700100002 TITLE Excitation functions of Ag-109(n,2n)Ag-108m, 2224700100003 Eu-151(n,2n)Eu-150m and Tb-159(n,2n)Tb-158 2224700100004 reactions from threshold to 15 MeV 2224700100005 REFERENCE (J,ARI,47,569,1996) final publ. 2224700100006 old data renormalized, new ones given 2224700100007 (S,INDC(NDS)-342,47,199602) prelim. renormal. data 2224700100008 (J,ARI,43,1065,1992) - prelim.data 2224700100009 INSTITUTE (2GERJUL) S.Q,F.C. and experimental site 2224700100010 (3HUNKOS) F.C.,J.C 2224700100011 AUTHOR (S.M.Qaim,F.Cserpak,J.Csikai) 2224700100012 FACILITY (CYCLO,2GERJUL) At 10-12 MeV - the Variable Energy 2224700100013 Compact CV28 Cyclotron,Institut FOR Chemistry,Yulich 2224700100014 (CYCLO,3HUNKOS) At 14.5MeV - MGC-20 in Debrecen 2224700100015 INC-SOURCE (D-D) Quasi-monoenergetic neutrons of energy between 2224700100016 8.7 MeV and 10.7 MeV were produced by bombarding a 2224700100017 deuterium gas target with deuterons of Energy between 2224700100018 6 and 8 MeV. 2224700100019 INC-SPECT The average neutron energy effective at the sample was2224700100020 calculated using a Monte Carlo program. 2224700100021 The neutron flux densities in front and at the back of2224700100022 the sample were determined via the Al-27(n,alpha) 2224700100023 monitor reaction whose cross section was taken from 2224700100024 the literature. The average neutron flux density 2224700100025 effective at the sample was then obtained taking into 2224700100026 account the flux distribution inside the sample. The 2224700100027 relative flux distribution inside the sample was 2224700100028 calculated both by Monte Carlo and numerical integrat.2224700100029 techniques. The calculated flux distribution was 2224700100030 finally normalised to the value from the front of 2224700100031 the Al monitor foil and the resulting absolute 2224700100032 distribution was averaged. Each flux density was 2224700100033 weighted with respect to its irradiation time. 2224700100034 SAMPLE Al monitor foils of 200 micro-m thickness were attached2224700100035 at the front and at the back of the tube. Each sample 2224700100036 was irradiated several times, each time with a fresh 2224700100037 Al monitor. Each sample was irradiated at 2224700100038 zero degree direction for between 7 to 10 hrs and 10 2224700100039 to 20 hrs, respectively. Measurements were carried out2224700100040 several months after irradiations and took about 3 2224700100041 days for each sample. 2224700100042 METHOD (ACTIV) The neutron activation technique was used. 2224700100043 DETECTOR (HPGE) 140 cm3 3 HPGe detector. 2224700100044 (GELI) The gamma activity of the irradiated samples 2224700100045 was measured using a Ge(Li) detector. 2224700100046 Also, it used for measurement the radioactivity of the 2224700100047 monitor reaction product (24Na). The peak area 2224700100048 analysis was done using the program Maestro. Due to 2224700100049 the large dimensions of the sample, the inhomogeneous 2224700100050 distribution of the activity and the low count rates, 2224700100051 the detection efficiency was determined following a 2224700100052 procedure which makes use of counting in various 2224700100053 geometry arrangements gamma-rays from a standard 2224700100054 source and from the samples. Self-absorption 2224700100055 was measured by placing an unirradiated absorbent 2224700100056 of material and geometry similar to the those of the 2224700100057 samples between the source and the detector. 2224700100058 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) The monitor cross 2224700100059 sections were taken from IRDF,1990. 2224700100060 DECAY-MON (11-NA-24,15.0HR,DG,1368.,1.) 2224700100061 CORRECTION The activity of the monitor product was corrected 2224700100062 for background contributions. The correction due to 2224700100063 breakup of deuterons on D2 gas was negligible. 2224700100064 Corrections for background neutrons and for coinciden-2224700100065 ce were applied. The latter was estimated from the 2224700100066 decay scheme and the effective detector efficiency. 2224700100067 ERR-ANALYS (ERR-T) Total uncertainty. Principal sources are: 2224700100068 (ERR-1) Uncertainty in sample weight 2224700100069 (ERR-2) Uncertainty of irradiation time 2224700100070 (ERR-3) Uncertainty in irradiation geometry and beam 2224700100071 deviation 2224700100072 (ERR-4,4.,6.) Uncertainty in correction for activity 2224700100073 induced by background neutrons (gas in/out, breakup) 2224700100074 (ERR-5,4.,6.) Error in excitation function of monitor 2224700100075 reaction 2224700100076 (ERR-6,,2.) The error the averaging of neutron flux 2224700100077 (ERR-7) Error in peak area analysis 2224700100078 (ERR-S,1.,3.) Error in statistics of gamma counting 2224700100079 (ERR-8) Uncertainty in the efficiency of the detector 2224700100080 (ERR-9) Uncertainty in the decay-data 2224700100081 HISTORY (19930701C) N.O. 2224700100082 (19970311U) Facility code corrected 2224700100083 (20000106A) Corrected by S.M. - dates changed 2224700100084 two new Subents added 2224700100085 (20011023A) . . Subent 004 corrected by S.M. 2224700100086 (20011023U) Last checking has been done. 2224700100087 (20151214A) SD: DECAY-DATA corrected in Subents 002,0042224700100088 BIB update following last publ.: Title corrected;SAMPLE2224700100089 moved to Subents 002-006; DECAY-MON added; 2nd cyclotr.2224700100090 added; etc. Cosmetic corrections in all Subents. 2224700100091 Ref. ARI,43,1065,1992 was added instead of W,Qaim,1993.2224700100092 ERR-ANALYS update. 2224700100093 (20200808U) SD: Small correction in ref. 2224700100094 ENDBIB 92 0 2224700100095 COMMON 6 3 2224700100096 ERR-1 ERR-2 ERR-3 ERR-7 ERR-8 ERR-9 2224700100097 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2224700100098 0.1 0.1 3. 3. 4. 1. 2224700100099 ENDCOMMON 3 0 2224700100100 ENDSUBENT 99 0 2224700199999 SUBENT 22247002 20151214 22462224700200001 BIB 5 12 2224700200002 REACTION (63-EU-151(N,2N)63-EU-150-G,,SIG) 2224700200003 DECAY-DATA (63-EU-150-G,35.8YR,DG,334.,0.94) 2224700200004 SAMPLE High purity Eu2O3 (99.99% 4.5g) was filled in a 2224700200005 polyethylene tube (1.6cm diam.x 4.3cm; 2224700200006 wall thickness = 0.1 cm) and Al monitor foils (200mu-m 2224700200007 thick) attached at the front and at the back of the 2224700200008 tube. 2224700200009 STATUS (TABLE) Data from priv.comm. in 1993; the same in Tbl.32224700200010 of ARI,43,1065,1992 2224700200011 (SPSDD,22247004) Corrected data are given in main ref 2224700200012 HISTORY (20151214A) SD: Eu-150m -> Eu-150g following half-life 2224700200013 in DECAY-DATA and REACTION code. 2224700200014 ENDBIB 12 0 2224700200015 NOCOMMON 0 0 2224700200016 DATA 4 3 2224700200017 EN EN-ERR DATA ERR-T 2224700200018 MEV MEV MB MB 2224700200019 9.72 0.13 185. 26. 2224700200020 10.21 0.14 270. 30. 2224700200021 10.7 0.14 382. 37. 2224700200022 ENDDATA 5 0 2224700200023 ENDSUBENT 22 0 2224700299999 SUBENT 22247003 20151214 22462224700300001 BIB 5 9 2224700300002 REACTION (65-TB-159(N,2N)65-TB-158,,SIG) 2224700300003 DECAY-DATA (65-TB-158-G,150.3YR,DG,944.,0.43) 2224700300004 SAMPLE Samples were made of high purity Tb4O7 (99.999% and 2224700300005 10 g) contained in a polythene tube of 1.6 cm diam., 2224700300006 4.3 cm length and 0.1 cm in thickness. 2224700300007 STATUS (TABLE) Data from priv.comm. in 1993; the same in Tbl.32224700300008 of ARI,43,1065,1992 2224700300009 (SPSDD,22247005) Corrected data are given in main ref 2224700300010 HISTORY (20151214A) SD: SF4=Tb-158g -> Tb-158 in REACTION code.2224700300011 ENDBIB 9 0 2224700300012 NOCOMMON 0 0 2224700300013 DATA 4 4 2224700300014 EN EN-ERR DATA ERR-T 2224700300015 MEV MEV MB MB 2224700300016 8.73 0.13 64. 25. 2224700300017 9.72 0.13 312. 30. 2224700300018 10.21 0.14 491. 54. 2224700300019 10.7 0.14 787. 94. 2224700300020 ENDDATA 6 0 2224700300021 ENDSUBENT 20 0 2224700399999 SUBENT 22247004 20151214 22462224700400001 BIB 5 14 2224700400002 REACTION (63-EU-151(N,2N)63-EU-150-G,,SIG) 2224700400003 DECAY-DATA (63-EU-150-G,36.9YR,DG,334.,0.960,DG,439.,0.803) 2224700400004 SAMPLE Three Eu203 samples (99.999% pure) were pressed at 2224700400005 10 t/cm2 to obtain 2 cm in diam. x 0.4 cm thick pellets2224700400006 (wt ~ 4.3 g). Each one of them was placed in an 2224700400007 Al-capsule and sandwiched between two Al foils. 2224700400008 STATUS (TABLE) Data from Tables 1, 2 of ARI,47,(5/6),569,1996 2224700400009 HISTORY (20000112C) Compiled by S.M. 2224700400010 (20011024A) Cross-section value for En=9.6 MeV 2224700400011 corrected from 290 to 250 mb 2224700400012 (20011023U) Last checking has been done. 2224700400013 (20151214A) SD: Eu-150m -> Eu-150g following half-life 2224700400014 in DECAY-DATA and REACTION code. HL=35.8yr -> 36.9yr in2224700400015 DECAY-DATA. STATUS 'COREL' deleted. 2224700400016 ENDBIB 14 0 2224700400017 NOCOMMON 0 0 2224700400018 DATA 4 6 2224700400019 EN EN-ERR DATA ERR-T 2224700400020 MEV MEV MB MB 2224700400021 9.18 0.24 164. 23. 2224700400022 9.60 0.24 250. 28. 2224700400023 10.10 0.24 335. 32. 2224700400024 10.83 0.30 849. 102. 2224700400025 11.20 0.30 952. 142. 2224700400026 12.14 0.30 982. 127. 2224700400027 ENDDATA 8 0 2224700400028 ENDSUBENT 27 0 2224700499999 SUBENT 22247005 20151214 22462224700500001 BIB 5 12 2224700500002 REACTION (65-TB-159(N,2N)65-TB-158,,SIG) 2224700500003 DECAY-DATA (65-TB-158-G,180.3YR,DG,944.,0.439) 2224700500004 SAMPLE Tb407 sample (99.999% pure) was pressed at 10. t/cm2 to2224700500005 obtain 2 cm in diam. x 0.4 cm thick pellet (wt~4.2 g),2224700500006 placed in an Al-capsule and sandwiched between two 2224700500007 Al foils. 2224700500008 STATUS (TABLE) Data from Tables 1, 2 of ARI,47,(5/6),569,1996 2224700500009 HISTORY (20000112C) Compiled by S.M. 2224700500010 (20000116U) Last checking has been done. 2224700500011 (20151214A) SD: HL=150.yr -> 180.yr following text of 2224700500012 the article (ARI,47,(5/6),569,1996). SF4=Tb-158g -> 2224700500013 Tb-158 in REACTION code. STATUS 'COREL' deleted. 2224700500014 ENDBIB 12 0 2224700500015 NOCOMMON 0 0 2224700500016 DATA 4 4 2224700500017 EN EN-ERR DATA ERR-T 2224700500018 MEV MEV MB MB 2224700500019 9.18 0.24 333. 32. 2224700500020 9.6 0.24 547. 60. 2224700500021 10.1 0.24 828. 99. 2224700500022 10.83 0.3 1410. 145. 2224700500023 ENDDATA 6 0 2224700500024 ENDSUBENT 23 0 2224700599999 SUBENT 22247006 20151214 22462224700600001 BIB 5 14 2224700600002 REACTION (47-AG-109(N,2N)47-AG-108-M,,SIG) 2224700600003 DECAY-DATA (47-AG-108-M,433.YR,DG,434.,0.905, 2224700600004 DG,614.,0.898, 2224700600005 DG,723.,0.908) 2224700600006 SAMPLE (47-AG-109,ENR=0.9926) Ag-109 powder (99.26% enriched) 2224700600007 was pressed at 10 t/cm2 to obtain a thin pellet of 2224700600008 1.3 cm in diam. (wt ~0.16g). Three such pellets 2224700600009 were prepared and each of them was sandwiched 2224700600010 between two Al foils. 2224700600011 For measurement at 14.5 MeV, 1.9 cm in diam. x 0.05 cm 2224700600012 thick high purity Ag samples were used. 2224700600013 STATUS (TABLE) Data from Table 1 of ARI,47,(5/6),569,1996 2224700600014 HISTORY (20000112C) Compiled by S.M. 2224700600015 (20000116U) Last checking has been done. 2224700600016 ENDBIB 14 0 2224700600017 NOCOMMON 0 0 2224700600018 DATA 4 3 2224700600019 EN EN-ERR DATA ERR-T 2224700600020 MEV MEV MB MB 2224700600021 10.86 0.36 276. 36. 2224700600022 12.17 0.3 451. 58. 2224700600023 14.5 0.25 697. 60. 2224700600024 ENDDATA 5 0 2224700600025 ENDSUBENT 24 0 2224700699999 ENDENTRY 6 0 2224799999999