ENTRY 22763 20180316 227022763 0 1 SUBENT 22763001 20180316 227022763 1 1 BIB 17 77 22763 1 2 TITLE Excitation functions of natTi(n,x)46,47,48Sc processes 22763 1 3 in the energy range of 12.5 - 19.6 MeV 22763 1 4 AUTHOR (N.I.Molla, S.M.Qaim, H.Liskien, R.Widera) 22763 1 5 INSTITUTE (2GERJUL,2ZZZGEL) 22763 1 6 REFERENCE (J,ARI,42,337,1991) Main reference 22763 1 7 REL-REF (M,,H.Lisken+,J,ARI,41,83,1990) Details of exp. method.22763 1 8 SAMPLE About 5g Ti metal powder (>99.9%) was pressed at 22763 1 9 10t/cm2 and disk (2cm in diam., 0.5 cm - thick) was 22763 1 10 obtained. Fifteen such samples, each sandwiched 22763 1 11 between pairs of aluminum sheets (2 cm diam. x0.1cm), 22763 1 12 were suspended from a graduated ring. 22763 1 13 FACILITY (VDG,2ZZZGEL) 22763 1 14 INC-SOURCE (D-T) A 3 mg/cm2 T-Ti target was used. The target 22763 1 15 was backed by a 4 cm diameter silver sheet of 0.3 mm 22763 1 16 thickness, fixed in an aluminum tube of 1 mm wall 22763 1 17 thickness. The silver sheet was cooled by a thin 22763 1 18 water film. 22763 1 19 INC-SPECT Neutron flux density is given as MISC in Subent 002. 22763 1 20 METHOD (ACTIV) The samples were activated in different 22763 1 21 angular positions with respect to the beam direction. 22763 1 22 In this way the neutron energy variation with angle 22763 1 23 from the source reaction could be used for the exci- 22763 1 24 tation function measurement. 22763 1 25 (GSPEC) Gamma-ray spectroscopy. 22763 1 26 DETECTOR (GELI) 35 cm**3 Ge(Li) detector to measure sample 22763 1 27 activity induced. 22763 1 28 MONITOR 1(1-H-1(N,EL)1-H-1,,DA) A proton recoil telescope, 22763 1 29 positioned at an angle of 16 degrees relative to the 22763 1 30 deuteron beam direction and at a source to radiator 22763 1 31 distance of 80 cm, was used for the absolute fluence 22763 1 32 determination. The fluence at other angles was deter- 22763 1 33 mined by using the known angular distribution of the 22763 1 34 source reaction. The fluence rates averaged over the 22763 1 35 sample volumes were in the range 0.6 to 1.8E+6 22763 1 36 neutrons/cm**2/sec. 22763 1 37 2(13-AL-27(N,A)11-NA-24,,SIG) 22763 1 38 In addition, the activities from the 13-Al-27(N,A)- 22763 1 39 reaction in the aluminum foils were detected with 22763 1 40 gamma-ray spectroscopy using the same equipment as 22763 1 41 for the activity measurements for the molybdenum 22763 1 42 sheets. 22763 1 43 MONIT-REF 1(,C.A.Uttley,R,IAEA-227,3,1983) 22763 1 44 2(,H.Vonach,R,IAEA-227,59,1983) 22763 1 45 References for neutron flux monitoring. 22763 1 46 CORRECTION .The neutron fluence measurements with the recoil te- 22763 1 47 lescope were corrected for distortions by the target 22763 1 48 assembly. The activation of the samples were correc- 22763 1 49 ted for the neutron source intensity variations with 22763 1 50 time, neutron attenuation and multiple scattering. 22763 1 51 The count rate in the activity measurements were cor-22763 1 52 rected for the small differences between counting and22763 1 53 calibration geometry, for coincidence and pile-up 22763 1 54 losses and for gamma self-absorption within the 22763 1 55 samples. 22763 1 56 .Corrections were made for: 22763 1 57 - Deviation from calibration geometry - 0.8%; 22763 1 58 - Gamma-ray absorption within the sample - 2.4 -11.7%;22763 1 59 - Coincident events - 4.5%; 22763 1 60 - Activity uncertainty - 4.0 - 5.1% 22763 1 61 ERR-ANALYS (ERR-T) Total uncertainty about 6%. Main uncertainty 22763 1 62 contributions in the neutron fluence measurements and 22763 1 63 in the activity measurements. 22763 1 64 (EN-ERR) Scale error 22763 1 65 (ERR-1) Total fluence uncertainty -3%. 22763 1 66 Total uncertainty in determination of absolute 22763 1 67 activity - 4. - 5. % . 22763 1 68 STATUS (TABLE) Table 1 from Appl.Rad.Isot.42(1991)337 22763 1 69 HISTORY (20031110C) 22763 1 70 (20060330U) Correction in according to Memo CP-E/089. 22763 1 71 (M.M.) 22763 1 72 (20090215A) M.M. Correction of misprint in Subent 003. 22763 1 73 BIB information was added. MISC and MISC-ERR were 22763 1 74 added in Subent 002. COMMON was added. 22763 1 75 (20100714A) M.M. Subent 002 was corrected. 22763 1 76 (20180316A) SD: MISC and MISC-ERR were added to Subents22763 1 77 003, 004. REACTION code corrected in Subents 003,004 22763 1 78 according to remark from V.Semkova. 22763 1 79 ENDBIB 77 0 22763 1 80 COMMON 1 3 22763 1 81 ERR-1 22763 1 82 PER-CENT 22763 1 83 3. 22763 1 84 ENDCOMMON 3 0 22763 1 85 ENDSUBENT 84 0 22763 199999 SUBENT 22763002 20100714 22222276300200001 BIB 5 12 2276300200002 REACTION ((22-TI-46(N,P)21-SC-46,,SIG)+ 2276300200003 (22-TI-47(N,X)21-SC-46,,SIG,,RAB)) 2276300200004 ANALYSIS Cross-section normalized to 46-Ti (abundance 8.2%),i.e 2276300200005 assuming that Ti-46(N,P)Sc-48 reaction is the only 2276300200006 contributing process. Contribution of Ti-47(N,NP) 2276300200007 process to formation of Sc-46 was expected to be small.2276300200008 DECAY-DATA (21-SC-46,84.0D,DG,889.,1.,DG,1121.,1.) 2276300200009 MISC-COL (MISC) Neutron flux density, 10**6 1/cm**2/sec. 2276300200010 Average of two measurements. 2276300200011 HISTORY (20100714A) M.M. REACTION was corrected according to 2276300200012 comment W.Mannhart (NDS web-site): 2276300200013 22-TI-0(N,X)21-SC-46,,SIG -> 2276300200014 ENDBIB 12 0 2276300200015 NOCOMMON 0 0 2276300200016 DATA 6 15 2276300200017 EN EN-ERR DATA ERR-T MISC MISC-ERR 2276300200018 MEV MEV MB MB SEE TEXT SEE TEXT 2276300200019 12.59 0.22 294. 18. 0.276 0.008 2276300200020 12.64 0.21 303. 18. 0.254 0.007 2276300200021 13.39 0.30 305. 18. 0.265 0.007 2276300200022 13.43 0.30 312. 19. 0.252 0.007 2276300200023 14.36 0.36 299. 18. 0.277 0.007 2276300200024 14.39 0.35 294. 18. 0.267 0.007 2276300200025 15.82 0.37 299. 18. 0.261 0.008 2276300200026 15.84 0.38 287. 17. 0.274 0.008 2276300200027 16.90 0.37 289. 17. 0.338 0.010 2276300200028 16.96 0.37 282. 17. 0.368 0.011 2276300200029 17.92 0.35 310. 19. 0.408 0.012 2276300200030 17.99 0.35 294. 18. 0.436 0.012 2276300200031 18.81 0.26 320. 19. 0.509 0.014 2276300200032 18.88 0.25 315. 19. 0.532 0.015 2276300200033 19.58 0.23 349. 21. 0.731 0.022 2276300200034 ENDDATA 17 0 2276300200035 ENDSUBENT 34 0 2276300299999 SUBENT 22763003 20180316 227022763 3 1 BIB 4 15 22763 3 2 REACTION ((22-TI-47(N,P)21-SC-47,,SIG,,FCT)+ 22763 3 3 (22-TI-48(N,X)21-SC-47,,SIG,,FCT)) 22763 3 4 Cross-section normalized to 47-Ti + 48-Ti (summed 22763 3 5 abundance 81.2%). Contribution of Ti-47(n,p) and 22763 3 6 Ti-48(n,np) were considered. Contribution of (n,np) was22763 3 7 not negligible since Ti-48 abundance is about 10 times 22763 3 8 higher than that of Ti-47. 22763 3 9 DECAY-DATA (21-SC-47,3.42D,DG,159.,0.685) 22763 3 10 MISC-COL (MISC) Neutron flux density, 10**6 1/cm**2/sec. 22763 3 11 Average of two measurements. 22763 3 12 HISTORY (20090215A) Misprint in abundance was corrected. 22763 3 13 (20180316A) SD: Instead of one REACTION code presented 22763 3 14 as sum of reactions using different targets (Ti-0 -> 22763 3 15 Ti-47 and Ti-48). MISC and MISC-ERR were added. 22763 3 16 ANALYSIS deleted (info moved to REACTION code). 22763 3 17 ENDBIB 15 0 22763 3 18 NOCOMMON 0 0 22763 3 19 DATA 6 15 22763 3 20 EN EN-ERR DATA ERR-T MISC MISC-ERR 22763 3 21 MEV MEV MB MB SEE TEXT SEE TEXT 22763 3 22 12.59 0.22 17.1 1.1 0.276 0.008 22763 3 23 12.64 0.21 18.9 1.1 0.254 0.007 22763 3 24 13.39 0.30 17.8 1.1 0.265 0.007 22763 3 25 13.43 0.30 21.8 1.3 0.252 0.007 22763 3 26 14.36 0.36 25.3 1.5 0.277 0.007 22763 3 27 14.39 0.35 27.1 1.6 0.267 0.007 22763 3 28 15.82 0.37 46.5 2.8 0.261 0.008 22763 3 29 15.84 0.38 43.8 2.6 0.274 0.008 22763 3 30 16.90 0.37 68.7 4.1 0.338 0.010 22763 3 31 16.96 0.37 61.6 3.7 0.368 0.011 22763 3 32 17.92 0.35 87.1 5.2 0.408 0.012 22763 3 33 17.99 0.35 82.6 5.0 0.436 0.012 22763 3 34 18.81 0.26 110.0 6.6 0.509 0.014 22763 3 35 18.88 0.25 99.2 6.0 0.532 0.015 22763 3 36 19.58 0.23 117.5 7.1 0.731 0.022 22763 3 37 ENDDATA 17 0 22763 3 38 ENDSUBENT 37 0 22763 399999 SUBENT 22763004 20180316 227022763 4 1 BIB 6 12 22763 4 2 REACTION ((22-TI-48(N,P)21-SC-48,,SIG)+ 22763 4 3 (22-TI-49(N,X)21-SC-48,,SIG,,RAB)) 22763 4 4 SAMPLE (22-TI-49,NAT=0.0541) 22763 4 5 ANALYSIS Cross-section normalized to 48-Ti (abundance 73.8%), 22763 4 6 assuming that the Ti-48(n,p) is the only contributing 22763 4 7 reaction. 22763 4 8 DECAY-DATA (21-SC-48,1.82D,DG,984.,1.,DG,1038.,0.975,DG,1312.,1.) 22763 4 9 MISC-COL (MISC) Neutron flux density, 10**6 1/cm**2/sec. 22763 4 10 Average of two measurements. 22763 4 11 HISTORY (20180316A) SD: Instead of one REACTION code presented 22763 4 12 as sum of reactions using different targets (Ti-0 -> 22763 4 13 Ti-47 and Ti-48). MISC and MISC-ERR were added. 22763 4 14 ENDBIB 12 0 22763 4 15 NOCOMMON 0 0 3 22763 4 16 DATA 6 15 22763 4 17 EN EN-ERR DATA ERR-T MISC MISC-ERR 22763 4 18 MEV MEV MB MB SEE TEXT SEE TEXT 22763 4 19 12.59 0.22 57.6 3.5 0.276 0.008 22763 4 20 12.64 0.21 58.8 3.5 0.254 0.007 22763 4 21 13.39 0.30 65.0 3.9 0.265 0.007 22763 4 22 13.43 0.30 63.4 3.8 0.252 0.007 22763 4 23 14.36 0.36 68.7 4.1 0.277 0.007 22763 4 24 14.39 0.35 67.7 4.1 0.267 0.007 22763 4 25 15.82 0.37 64.0 3.8 0.261 0.008 22763 4 26 15.84 0.38 62.5 3.7 0.274 0.008 22763 4 27 16.90 0.37 56.5 3.4 0.338 0.010 22763 4 28 16.96 0.37 55.2 3.3 0.368 0.011 22763 4 29 17.92 0.35 51.4 3.1 0.408 0.012 22763 4 30 17.99 0.35 50.6 3.1 0.436 0.012 22763 4 31 18.81 0.26 46.1 2.8 0.509 0.014 22763 4 32 18.88 0.25 44.7 2.7 0.532 0.015 22763 4 33 19.58 0.23 43.9 2.6 0.731 0.022 22763 4 34 ENDDATA 17 0 22763 4 35 ENDSUBENT 34 0 22763 499999 ENDENTRY 4 0 2276399999999