ENTRY F1469 20230113 F094F1469 0 1 SUBENT F1469001 20230113 F094F1469 1 1 BIB 14 36 F1469 1 2 TITLE New data on Ho(alpha,x) reactions and the aspects of F1469 1 3 167Tm and 165Er production for medical use F1469 1 4 AUTHOR (E.S.Kormazeva,I.A.Khomenko,V.N.Unezhev,R.A.Aliev) F1469 1 5 REFERENCE (J,JRN,331,4259,2022) F1469 1 6 #doi:10.1007/s10967-022-08464-1 F1469 1 7 INSTITUTE (4RUSKUR) F1469 1 8 FACILITY (ISOCY,4RUSKUR) U-150 isochronous cyclotron F1469 1 9 SAMPLE The holmium oxide Ho2O3 ~ 50 mg (99.99 %, purity, + F1469 1 10 1-2 % dinitrocellulose, 11 layers) was used. The Ho2O3F1469 1 11 layers with a thickness of 3-16 + - 10% mg/cm2 and a F1469 1 12 spot diameter of 20 mm were obtained as a result of F1469 1 13 sedimentation and after drying at room temperature. F1469 1 14 The aluminum foil (8.4 + -0.5 mu-m) was used for the F1469 1 15 protection of the layer from mechanical damage. F1469 1 16 INC-SOURCE Beam current was 120 nA, beam diameter was ~ 18 mm. F1469 1 17 DETECTOR (HPGE) Gamma spectrometer with an ORTEC GEM 35P4 high F1469 1 18 purity germanium detector with energy resolution 850 eVF1469 1 19 for the 122 keV line and 1.8 keV for the 1330 keV line F1469 1 20 was used. F1469 1 21 METHOD (ACTIV,STTA) Irradiation time was 20 minutes. F1469 1 22 (EDEG) Al foils (~ 20 and ~30 mu-m) were used as F1469 1 23 degraders. F1469 1 24 MONITOR (13-AL-27(A,X)11-NA-24,,SIG) F1469 1 25 (22-TI-0(A,X)24-CR-51,,SIG) F1469 1 26 (29-CU-0(A,X)30-ZN-65,,SIG) F1469 1 27 (29-CU-0(A,X)31-GA-66,,SIG) F1469 1 28 (29-CU-0(A,X)31-GA-67,,SIG) F1469 1 29 ADD-RES (COMP) The measured excitation functions were compared F1469 1 30 with the data from TENDL-2019 and TENDL-2021 libraries F1469 1 31 and the previous experimental values. F1469 1 32 (TTY-C) The reaction Ho-165(A,4N)Tm-165 -> Er-165 was F1469 1 33 considered a potential method for the production of F1469 1 34 Er-165. F1469 1 35 ERR-ANALYS Uncertainty of the beam current was 10%. F1469 1 36 STATUS (APRVD) Entry was approved by Dr. E.S.Kormazeva. F1469 1 37 HISTORY (20230113C) F1469 1 38 ENDBIB 36 0 F1469 1 39 NOCOMMON 0 0 F1469 1 40 ENDSUBENT 39 0 F1469 199999 SUBENT F1469002 20230113 F094F1469 2 1 BIB 5 14 F1469 2 2 REACTION (67-HO-165(A,6N)69-TM-163,,SIG) F1469 2 3 ANALYSIS (DECAY) F1469 2 4 DECAY-DATA (69-TM-163,1.810HR,DG,104.32,0.186, F1469 2 5 DG,241.305,0.109, F1469 2 6 DG,299.667,0.0456) F1469 2 7 ERR-ANALYS (ERR-T) The uncertainties of the cross sections were F1469 2 8 determined by taking the sum in quadrature of all F1469 2 9 individual linear contributions: F1469 2 10 (ERR-1) uncertainty of nuclear data; F1469 2 11 (ERR-2) uncertainty of efficiency calibration; F1469 2 12 (ERR-3) uncertainty of layers' thickness determination;F1469 2 13 (ERR-4,10.,30.) uncertainty of photo peak area. F1469 2 14 STATUS (TABLE) Tbl.3 from Journal of Rad.Nucl.Chem. 331,4259, F1469 2 15 2022 F1469 2 16 ENDBIB 14 0 F1469 2 17 COMMON 3 3 F1469 2 18 ERR-1 ERR-2 ERR-3 F1469 2 19 PER-CENT PER-CENT PER-CENT F1469 2 20 3. 5. 10. F1469 2 21 ENDCOMMON 3 0 F1469 2 22 DATA 4 2 F1469 2 23 EN EN-ERR DATA ERR-T F1469 2 24 MEV MEV MB MB F1469 2 25 58.8 0.6 40.1 7.0 F1469 2 26 55.5 0.7 2.9 0.9 F1469 2 27 ENDDATA 4 0 F1469 2 28 ENDSUBENT 27 0 F1469 299999 SUBENT F1469003 20230113 F094F1469 3 1 BIB 5 14 F1469 3 2 REACTION (67-HO-165(A,4N)69-TM-165,,SIG) F1469 3 3 ANALYSIS (DECAY) F1469 3 4 DECAY-DATA (69-TM-165,30.06HR,DG,242.917,0.355, F1469 3 5 DG,297.369,0.127, F1469 3 6 DG,806.372,0.095) F1469 3 7 ERR-ANALYS (ERR-T) The uncertainties of the cross sections were F1469 3 8 determined by taking the sum in quadrature of all F1469 3 9 individual linear contributions: F1469 3 10 (ERR-1) uncertainty of nuclear data; F1469 3 11 (ERR-2) uncertainty of efficiency calibration; F1469 3 12 (ERR-3) uncertainty of layers' thickness determination;F1469 3 13 (ERR-4,10.,30.) uncertainty of photo peak area. F1469 3 14 STATUS (TABLE) Tbl.3 from Journal of Rad.Nucl.Chem. 331,4259, F1469 3 15 2022 F1469 3 16 ENDBIB 14 0 F1469 3 17 COMMON 3 3 F1469 3 18 ERR-1 ERR-2 ERR-3 F1469 3 19 PER-CENT PER-CENT PER-CENT F1469 3 20 3. 5. 10. F1469 3 21 ENDCOMMON 3 0 F1469 3 22 DATA 4 9 F1469 3 23 EN EN-ERR DATA ERR-T F1469 3 24 MEV MEV MB MB F1469 3 25 58.8 0.6 385.0 84.9 F1469 3 26 55.5 0.7 596.9 129.3 F1469 3 27 52.5 0.9 839.0 180.2 F1469 3 28 49.7 1.1 1108.8 271.3 F1469 3 29 46.7 1.2 1036.5 226.1 F1469 3 30 44.0 1.4 868.0 191.0 F1469 3 31 40.8 1.6 536.7 133.8 F1469 3 32 37.7 1.9 110.8 32.8 F1469 3 33 34.4 2.1 9.1 4.0 F1469 3 34 ENDDATA 11 0 F1469 3 35 ENDSUBENT 34 0 F1469 399999 SUBENT F1469004 20230113 F094F1469 4 1 BIB 5 14 F1469 4 2 REACTION (67-HO-165(A,3N)69-TM-166,,SIG) F1469 4 3 ANALYSIS (DECAY) F1469 4 4 DECAY-DATA (69-TM-166-G,7.7HR,DG,778.814,0.191, F1469 4 5 DG,184.405,0.162, F1469 4 6 DG,1273.54,0.150) F1469 4 7 ERR-ANALYS (ERR-T) The uncertainties of the cross sections were F1469 4 8 determined by taking the sum in quadrature of all F1469 4 9 individual linear contributions: F1469 4 10 (ERR-1) uncertainty of nuclear data; F1469 4 11 (ERR-2) uncertainty of efficiency calibration; F1469 4 12 (ERR-3) uncertainty of layers' thickness determination;F1469 4 13 (ERR-4,10.,30.) uncertainty of photo peak area. F1469 4 14 STATUS (TABLE) Tbl.3 from Journal of Rad.Nucl.Chem. 331,4259, F1469 4 15 2022 F1469 4 16 ENDBIB 14 0 F1469 4 17 COMMON 3 3 F1469 4 18 ERR-1 ERR-2 ERR-3 F1469 4 19 PER-CENT PER-CENT PER-CENT F1469 4 20 3. 5. 10. F1469 4 21 ENDCOMMON 3 0 F1469 4 22 DATA 4 10 F1469 4 23 EN EN-ERR DATA ERR-T F1469 4 24 MEV MEV MB MB F1469 4 25 58.8 0.6 87.0 19.3 F1469 4 26 55.5 0.7 105.5 21.3 F1469 4 27 52.5 0.9 130.7 26.1 F1469 4 28 49.7 1.1 182.3 32.7 F1469 4 29 46.7 1.2 269.2 49.7 F1469 4 30 44.0 1.4 449.8 90.0 F1469 4 31 40.8 1.6 881.8 151.8 F1469 4 32 37.7 1.9 1079.3 210.1 F1469 4 33 34.4 2.1 795.8 145.3 F1469 4 34 31.0 2.4 445.4 78.7 F1469 4 35 ENDDATA 12 0 F1469 4 36 ENDSUBENT 35 0 F1469 499999 SUBENT F1469005 20230113 F094F1469 5 1 BIB 5 12 F1469 5 2 REACTION (67-HO-165(A,2N)69-TM-167,,SIG) F1469 5 3 ANALYSIS (DECAY) F1469 5 4 DECAY-DATA (69-TM-167,9.25D,DG,207.801,0.420) F1469 5 5 ERR-ANALYS (ERR-T) The uncertainties of the cross sections were F1469 5 6 determined by taking the sum in quadrature of all F1469 5 7 individual linear contributions: F1469 5 8 (ERR-1) uncertainty of nuclear data; F1469 5 9 (ERR-2) uncertainty of efficiency calibration; F1469 5 10 (ERR-3) uncertainty of layers' thickness determination;F1469 5 11 (ERR-4,10.,30.) uncertainty of photo peak area. F1469 5 12 STATUS (TABLE) Tbl.3 from Journal of Rad.Nucl.Chem. 331,4259, F1469 5 13 2022 F1469 5 14 ENDBIB 12 0 F1469 5 15 COMMON 3 3 F1469 5 16 ERR-1 ERR-2 ERR-3 F1469 5 17 PER-CENT PER-CENT PER-CENT F1469 5 18 3. 5. 10. F1469 5 19 ENDCOMMON 3 0 F1469 5 20 DATA 4 11 F1469 5 21 EN EN-ERR DATA ERR-T F1469 5 22 MEV MEV MB MB F1469 5 23 58.8 0.6 24.4 3.8 F1469 5 24 55.5 0.7 29.0 4.5 F1469 5 25 52.5 0.9 33.2 5.2 F1469 5 26 49.7 1.1 42.9 8.2 F1469 5 27 46.7 1.2 48.8 7.6 F1469 5 28 44.0 1.4 64.2 10.2 F1469 5 29 40.8 1.6 113.0 22.2 F1469 5 30 37.7 1.9 137.4 34.4 F1469 5 31 34.4 2.1 219.1 57.0 F1469 5 32 31.0 2.4 595.8 145.0 F1469 5 33 27.3 2.9 1125.0 250.0 F1469 5 34 ENDDATA 13 0 F1469 5 35 ENDSUBENT 34 0 F1469 599999 SUBENT F1469006 20230113 F094F1469 6 1 BIB 5 13 F1469 6 2 REACTION (67-HO-165(A,N)69-TM-168,,SIG) F1469 6 3 ANALYSIS (DECAY) F1469 6 4 DECAY-DATA (69-TM-168,93.1D,DG,198.25,0.5449, F1469 6 5 DG,815.99,0.3430) F1469 6 6 ERR-ANALYS (ERR-T) The uncertainties of the cross sections were F1469 6 7 determined by taking the sum in quadrature of all F1469 6 8 individual linear contributions: F1469 6 9 (ERR-1) uncertainty of nuclear data; F1469 6 10 (ERR-2) uncertainty of efficiency calibration; F1469 6 11 (ERR-3) uncertainty of layers' thickness determination;F1469 6 12 (ERR-4,10.,30.) uncertainty of photo peak area. F1469 6 13 STATUS (TABLE) Tbl.3 from Journal of Rad.Nucl.Chem. 331,4259, F1469 6 14 2022 F1469 6 15 ENDBIB 13 0 F1469 6 16 COMMON 3 3 F1469 6 17 ERR-1 ERR-2 ERR-3 F1469 6 18 PER-CENT PER-CENT PER-CENT F1469 6 19 3. 5. 10. F1469 6 20 ENDCOMMON 3 0 F1469 6 21 DATA 4 11 F1469 6 22 EN EN-ERR DATA ERR-T F1469 6 23 MEV MEV MB MB F1469 6 24 58.8 0.6 1.3 0.5 F1469 6 25 55.5 0.7 1.5 0.6 F1469 6 26 52.5 0.9 1.7 0.7 F1469 6 27 49.7 1.1 1.8 0.7 F1469 6 28 46.7 1.2 2.9 0.8 F1469 6 29 44.0 1.4 2.7 0.9 F1469 6 30 40.8 1.6 3.7 1.1 F1469 6 31 37.7 1.9 5.2 1.1 F1469 6 32 34.4 2.1 5.4 1.5 F1469 6 33 31.0 2.4 8.3 1.9 F1469 6 34 27.3 2.9 11.5 2.3 F1469 6 35 ENDDATA 13 0 F1469 6 36 ENDSUBENT 35 0 F1469 699999 SUBENT F1469007 20230113 F094F1469 7 1 BIB 4 6 F1469 7 2 REACTION (67-HO-165(A,2N)69-TM-167,,TTY,,PHY,DERIV) F1469 7 3 ANALYSIS (INTEF) F1469 7 4 DECAY-DATA (69-TM-167,9.25D,DG,207.801,0.420) F1469 7 5 STATUS (TABLE) Tbl.5 from Journal of Rad.Nucl.Chem. 331,4259, F1469 7 6 2022 F1469 7 7 (DEP,F1469005) Excitation function F1469 7 8 ENDBIB 6 0 F1469 7 9 NOCOMMON 0 0 F1469 7 10 DATA 4 1 F1469 7 11 EN-MAX EN-MIN TIME-IRRD DATA F1469 7 12 MEV MEV MIN MBQ/MUAHR F1469 7 13 35. 25. 20. 2.22 F1469 7 14 ENDDATA 3 0 F1469 7 15 ENDSUBENT 14 0 F1469 799999 ENDENTRY 7 0 F146999999999