ENTRY F1472 20230120 F094F1472 0 1 SUBENT F1472001 20230120 F094F1472 1 1 BIB 13 42 F1472 1 2 TITLE New method for production of 155Tb via 155Dy by F1472 1 3 irradiation of natGd by medium energy alpha particles F1472 1 4 AUTHOR (A.N.Moiseeva,R.A.Aliev,E.B.Furkina,V.I.Novikov, F1472 1 5 V.N.Unezhev) F1472 1 6 INSTITUTE (4RUSKUR) F1472 1 7 REFERENCE (J,NMB,106-107,52,2022) F1472 1 8 #doi:10.1016/j.nucmedbio.2021.12.004 F1472 1 9 FACILITY (ISOCY,4RUSKUR) U-150 isochronous cyclotron F1472 1 10 SAMPLE Gadolinium oxide targets of natural isotopic F1472 1 11 composition (chemical purity 97%, main impurity Y <2%, F1472 1 12 Dy < 0.01%, Tb <0.07%) were used. The average F1472 1 13 thickness of each target was determined by weighing F1472 1 14 as 8-12 mu-m. The surface of each target was F1472 1 15 additionally covered with a thin 8.3 mu-m aluminum F1472 1 16 foil in order to prevent them from sticking together F1472 1 17 during irradiation. F1472 1 18 METHOD (STTA,EDEG) The cross sections were measured by the F1472 1 19 stack foil technique. F1472 1 20 (ACTIV) A target assembly was irradiated for 50 min, F1472 1 21 and an average current was of 0.1 mu-A. For each F1472 1 22 target, 3-4 measurements were made within 8 days F1472 1 23 after EOB. F1472 1 24 (GSPEC) F1472 1 25 DETECTOR (HPGE) The activity of the nuclear reaction products F1472 1 26 was measured on a gamma-ray spectrometer equipped with F1472 1 27 ORTEC GEM 35P4 high purity germanium detector with an F1472 1 28 energy resolution of 850 eV for the 122 keV line and F1472 1 29 1.8 keV for the 1.33 MeV line. The distance from the F1472 1 30 detector was chosen so that the dead time did not F1472 1 31 exceed 12%. F1472 1 32 MONITOR (13-AL-27(HE3,X)11-NA-24,,SIG) F1472 1 33 (22-TI-0(A,X)24-CR-51,,SIG) F1472 1 34 (29-CU-0(A,X)31-GA-66,,SIG) F1472 1 35 (29-CU-0(A,X)31-GA-67,,SIG) F1472 1 36 (29-CU-0(A,X)30-ZN-65,,SIG) F1472 1 37 ADD-RES (COMP) Comparison with data from TENDL-21 library was F1472 1 38 performed. F1472 1 39 ERR-ANALYS The uncertainty of the alpha particle energy on the F1472 1 40 target ranged 1.4-6.8 MeV, depending on the position F1472 1 41 of the target in the stack. F1472 1 42 STATUS (APRVD) Entry was approved by Dr. A.N.Moiseeva F1472 1 43 HISTORY (20230120C) F1472 1 44 ENDBIB 42 0 F1472 1 45 NOCOMMON 0 0 F1472 1 46 ENDSUBENT 45 0 F1472 199999 SUBENT F1472002 20230120 F094F1472 2 1 BIB 4 14 F1472 2 2 REACTION (64-GD-0(A,X)64-GD-159,,SIG) F1472 2 3 DECAY-DATA (64-GD-159,18.479HR,DG,363.53,0.1178) F1472 2 4 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 2 5 was calculated as the square root of the sum of the F1472 2 6 squares of the individual uncertainties: F1472 2 7 (ERR-1) uncertainty in determining the efficiency of F1472 2 8 the detector; F1472 2 9 (ERR-2,1.,10.) uncertainty in determining the F1472 2 10 photopeak area; F1472 2 11 (ERR-3) uncertainty in determining the target F1472 2 12 thickness; F1472 2 13 (ERR-4) uncertainty of nuclear data; F1472 2 14 (ERR-5) uncertainty of current value. F1472 2 15 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 2 16 ENDBIB 14 0 F1472 2 17 COMMON 4 3 F1472 2 18 ERR-1 ERR-3 ERR-4 ERR-5 F1472 2 19 PER-CENT PER-CENT PER-CENT PER-CENT F1472 2 20 7. 10. 3. 10. F1472 2 21 ENDCOMMON 3 0 F1472 2 22 DATA 4 17 F1472 2 23 EN EN-ERR DATA ERR-T F1472 2 24 MEV MEV MB MB F1472 2 25 58.9 1.5 11.7 2.1 F1472 2 26 57.1 1.6 15.5 2.5 F1472 2 27 55.2 1.8 17.7 3.0 F1472 2 28 53.3 1.9 13.7 9.0 F1472 2 29 51.3 2.0 19.3 4.7 F1472 2 30 49.3 2.2 17.2 8.1 F1472 2 31 47.5 2.4 12.5 2.0 F1472 2 32 45.4 2.6 10.3 2.9 F1472 2 33 43.5 2.7 13.6 2.4 F1472 2 34 41.2 3.0 9.5 1.8 F1472 2 35 38.4 3.3 7.8 1.3 F1472 2 36 35.3 3.7 6.0 1.2 F1472 2 37 33.0 3.9 3.6 0.7 F1472 2 38 30.0 4.4 2.2 0.5 F1472 2 39 26.8 4.9 1.5 0.9 F1472 2 40 23.2 5.7 0.24 0.20 F1472 2 41 20.3 6.4 0.49 0.35 F1472 2 42 ENDDATA 19 0 F1472 2 43 ENDSUBENT 42 0 F1472 299999 SUBENT F1472003 20230120 F094F1472 3 1 BIB 4 14 F1472 3 2 REACTION (64-GD-0(A,X)65-TB-153,CUM,SIG) F1472 3 3 DECAY-DATA (65-TB-153,3.24D,DG,212.00,0.310) F1472 3 4 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 3 5 was calculated as the square root of the sum of the F1472 3 6 squares of the individual uncertainties: F1472 3 7 (ERR-1) uncertainty in determining the efficiency of F1472 3 8 the detector; F1472 3 9 (ERR-2,1.,10.) uncertainty in determining the F1472 3 10 photopeak area; F1472 3 11 (ERR-3) uncertainty in determining the target F1472 3 12 thickness; F1472 3 13 (ERR-4) uncertainty of nuclear data; F1472 3 14 (ERR-5) uncertainty of current value. F1472 3 15 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 3 16 ENDBIB 14 0 F1472 3 17 COMMON 4 3 F1472 3 18 ERR-1 ERR-3 ERR-4 ERR-5 F1472 3 19 PER-CENT PER-CENT PER-CENT PER-CENT F1472 3 20 7. 10. 3. 10. F1472 3 21 ENDCOMMON 3 0 F1472 3 22 DATA 4 15 F1472 3 23 EN EN-ERR DATA ERR-T F1472 3 24 MEV MEV MB MB F1472 3 25 58.9 1.5 12.0 3.4 F1472 3 26 57.1 1.6 10.0 2.4 F1472 3 27 55.2 1.8 6.7 2.8 F1472 3 28 53.3 1.9 3.4 2.3 F1472 3 29 51.3 2.0 3.0 1.0 F1472 3 30 47.5 2.4 2.41 0.77 F1472 3 31 45.4 2.6 2.8 2.1 F1472 3 32 43.5 2.7 3.29 0.53 F1472 3 33 41.2 3.0 2.61 0.45 F1472 3 34 38.4 3.3 2.60 0.59 F1472 3 35 35.3 3.7 1.36 0.26 F1472 3 36 33.0 3.9 0.90 0.18 F1472 3 37 30.0 4.4 0.78 0.44 F1472 3 38 26.8 4.9 0.49 0.25 F1472 3 39 23.2 5.7 0.21 0.14 F1472 3 40 ENDDATA 17 0 F1472 3 41 ENDSUBENT 40 0 F1472 399999 SUBENT F1472004 20230120 F094F1472 4 1 BIB 4 14 F1472 4 2 REACTION (64-GD-0(A,X)65-TB-154-M1,CUM,SIG) F1472 4 3 DECAY-DATA (65-TB-154-M1,21.5HR,DG,123.07,0.26) F1472 4 4 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 4 5 was calculated as the square root of the sum of the F1472 4 6 squares of the individual uncertainties: F1472 4 7 (ERR-1) uncertainty in determining the efficiency of F1472 4 8 the detector; F1472 4 9 (ERR-2,1.,10.) uncertainty in determining the F1472 4 10 photopeak area; F1472 4 11 (ERR-3) uncertainty in determining the target F1472 4 12 thickness; F1472 4 13 (ERR-4) uncertainty of nuclear data; F1472 4 14 (ERR-5) uncertainty of current value. F1472 4 15 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 4 16 ENDBIB 14 0 F1472 4 17 COMMON 4 3 F1472 4 18 ERR-1 ERR-3 ERR-4 ERR-5 F1472 4 19 PER-CENT PER-CENT PER-CENT PER-CENT F1472 4 20 7. 10. 3. 10. F1472 4 21 ENDCOMMON 3 0 F1472 4 22 DATA 4 13 F1472 4 23 EN EN-ERR DATA ERR-T F1472 4 24 MEV MEV MB MB F1472 4 25 58.9 1.5 1.59 0.41 F1472 4 26 57.1 1.6 1.33 0.23 F1472 4 27 55.2 1.8 1.42 0.29 F1472 4 28 53.3 1.9 0.55 0.41 F1472 4 29 51.3 2.0 0.83 0.27 F1472 4 30 47.5 2.4 0.37 0.19 F1472 4 31 45.4 2.6 0.41 0.22 F1472 4 32 43.5 2.7 0.22 0.12 F1472 4 33 41.2 3.0 0.43 0.23 F1472 4 34 38.4 3.3 0.19 0.12 F1472 4 35 35.3 3.7 0.20 0.09 F1472 4 36 33.0 3.9 0.42 0.22 F1472 4 37 30.0 4.4 0.17 0.10 F1472 4 38 ENDDATA 15 0 F1472 4 39 ENDSUBENT 38 0 F1472 499999 SUBENT F1472005 20230120 F094F1472 5 1 BIB 4 17 F1472 5 2 REACTION 1(64-GD-0(A,X)65-TB-154-G,,SIG) F1472 5 3 2(64-GD-0(A,X)65-TB-154-M2,,SIG) F1472 5 4 DECAY-DATA (65-TB-154-G,9.4HR,DG,123.07,0.30,DG,346.70,0.016, F1472 5 5 DG,540.,0.20) F1472 5 6 (65-TB-154-M2,22.7HR,DG,127.07,0.43,DG,346.70,0.69) F1472 5 7 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 5 8 was calculated as the square root of the sum of the F1472 5 9 squares of the individual uncertainties: F1472 5 10 (ERR-1) uncertainty in determining the efficiency of F1472 5 11 the detector; F1472 5 12 (ERR-2,1.,10.) uncertainty in determining the F1472 5 13 photopeak area; F1472 5 14 (ERR-3) uncertainty in determining the target F1472 5 15 thickness; F1472 5 16 (ERR-4) uncertainty of nuclear data; F1472 5 17 (ERR-5) uncertainty of current value. F1472 5 18 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 5 19 ENDBIB 17 0 F1472 5 20 COMMON 4 3 F1472 5 21 ERR-1 ERR-3 ERR-4 ERR-5 F1472 5 22 PER-CENT PER-CENT PER-CENT PER-CENT F1472 5 23 7. 10. 3. 10. F1472 5 24 ENDCOMMON 3 0 F1472 5 25 DATA 6 13 F1472 5 26 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 2F1472 5 27 MEV MEV MB MB MB MB F1472 5 28 58.9 1.5 6.6 1.5 0.70 0.21F1472 5 29 57.1 1.6 7.4 1.2 0.62 0.10F1472 5 30 55.2 1.8 5.4 1.0 0.42 0.09F1472 5 31 53.3 1.9 2.28 1.63 0.41 0.345F1472 5 32 51.3 2.0 2.02 0.62 0.31 0.13F1472 5 33 49.3 2.2 2.27 1.37 F1472 5 34 47.5 2.4 0.56 0.27 0.17 0.12F1472 5 35 45.4 2.6 0.73 0.17 F1472 5 36 43.5 2.7 0.52 0.28 0.12 0.10F1472 5 37 41.2 3.0 0.33 0.18 0.10 0.08F1472 5 38 38.4 3.3 0.46 0.28 F1472 5 39 35.3 3.7 0.74 0.49 0.03 0.03F1472 5 40 33.0 3.9 0.42 0.19 F1472 5 41 ENDDATA 15 0 F1472 5 42 ENDSUBENT 41 0 F1472 599999 SUBENT F1472006 20230120 F094F1472 6 1 BIB 5 18 F1472 6 2 REACTION 1(64-GD-0(A,X)65-TB-155,,SIG) F1472 6 3 2(64-GD-0(A,X)65-TB-155,CUM,SIG) F1472 6 4 DECAY-DATA (65-TB-155,5.32D,DG,86.55,0.32,DG,105.32,0.251, F1472 6 5 DG,180.08,0.075,DG,262.27,0.053) F1472 6 6 CORRECTION 155Dy decay contribution subtracted. F1472 6 7 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 6 8 was calculated as the square root of the sum of the F1472 6 9 squares of the individual uncertainties: F1472 6 10 (ERR-1) uncertainty in determining the efficiency of F1472 6 11 the detector; F1472 6 12 (ERR-2,1.,10.) uncertainty in determining the F1472 6 13 photopeak area; F1472 6 14 (ERR-3) uncertainty in determining the target F1472 6 15 thickness; F1472 6 16 (ERR-4) uncertainty of nuclear data; F1472 6 17 (ERR-5) uncertainty of current value. F1472 6 18 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 6 19 (DEP,F1472008) 155Dy production cross section F1472 6 20 ENDBIB 18 0 F1472 6 21 COMMON 4 3 F1472 6 22 ERR-1 ERR-3 ERR-4 ERR-5 F1472 6 23 PER-CENT PER-CENT PER-CENT PER-CENT F1472 6 24 7. 10. 3. 10. F1472 6 25 ENDCOMMON 3 0 F1472 6 26 DATA 6 17 F1472 6 27 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 2F1472 6 28 MEV MEV MB MB MB MB F1472 6 29 58.9 1.5 33.61 5.52 217.3 38.2F1472 6 30 57.1 1.6 32.41 5.41 263.7 48.0F1472 6 31 55.2 1.8 28.22 4.63 277.8 49.7F1472 6 32 53.3 1.9 22.95 13.1 189. 110.F1472 6 33 51.3 2.0 25.72 4.17 234.9 40.5F1472 6 34 49.3 2.2 14.08 8.41 183.2 26.5F1472 6 35 47.5 2.4 19.92 3.04 184.9 29.5F1472 6 36 45.4 2.6 17.68 2.60 157.0 23.8F1472 6 37 43.5 2.7 10.19 1.56 146.9 23.5F1472 6 38 41.2 3.0 3.61 0.54 74.2 11.6F1472 6 39 38.4 3.3 4.87 0.84 51.5 9.4F1472 6 40 35.3 3.7 1.96 0.35 23.12 4.43F1472 6 41 33.0 3.9 1.60 0.39 13.76 2.30F1472 6 42 30.0 4.4 1.23 0.24 6.42 1.38F1472 6 43 26.8 4.9 0.97 0.18 1.63 0.37F1472 6 44 23.2 5.7 0.37 0.10F1472 6 45 20.3 6.4 0.51 0.12F1472 6 46 ENDDATA 19 0 F1472 6 47 ENDSUBENT 46 0 F1472 699999 SUBENT F1472007 20230120 F094F1472 7 1 BIB 4 16 F1472 7 2 REACTION (64-GD-0(A,X)65-TB-156,,SIG) F1472 7 3 DECAY-DATA (65-TB-156-G,5.35D,DG,88.97,0.18,DG,199.19,0.41, F1472 7 4 DG,356.38,0.136,DG,534.29,0.67, F1472 7 5 DG,1222.44,0.31) F1472 7 6 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 7 7 was calculated as the square root of the sum of the F1472 7 8 squares of the individual uncertainties: F1472 7 9 (ERR-1) uncertainty in determining the efficiency of F1472 7 10 the detector; F1472 7 11 (ERR-2,1.,10.) uncertainty in determining the F1472 7 12 photopeak area; F1472 7 13 (ERR-3) uncertainty in determining the target F1472 7 14 thickness; F1472 7 15 (ERR-4) uncertainty of nuclear data; F1472 7 16 (ERR-5) uncertainty of current value. F1472 7 17 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 7 18 ENDBIB 16 0 F1472 7 19 COMMON 4 3 F1472 7 20 ERR-1 ERR-3 ERR-4 ERR-5 F1472 7 21 PER-CENT PER-CENT PER-CENT PER-CENT F1472 7 22 7. 10. 3. 10. F1472 7 23 ENDCOMMON 3 0 F1472 7 24 DATA 4 16 F1472 7 25 EN EN-ERR DATA ERR-T F1472 7 26 MEV MEV MB MB F1472 7 27 58.9 1.5 28.99 5.70 F1472 7 28 57.1 1.6 33.03 6.24 F1472 7 29 55.2 1.8 34.36 6.30 F1472 7 30 53.3 1.9 22.8 13.2 F1472 7 31 51.3 2.0 26.61 4.58 F1472 7 32 49.3 2.2 14.14 4.65 F1472 7 33 47.5 2.4 18.54 3.11 F1472 7 34 45.4 2.6 15.02 2.57 F1472 7 35 43.5 2.7 15.12 2.46 F1472 7 36 41.2 3.0 8.68 1.51 F1472 7 37 38.4 3.3 7.30 1.23 F1472 7 38 35.3 3.7 4.11 0.68 F1472 7 39 33.0 3.9 2.43 0.43 F1472 7 40 30.0 4.4 1.73 0.33 F1472 7 41 26.8 4.9 0.75 0.17 F1472 7 42 23.2 5.7 0.42 0.08 F1472 7 43 ENDDATA 18 0 F1472 7 44 ENDSUBENT 43 0 F1472 799999 SUBENT F1472008 20230120 F094F1472 8 1 BIB 4 14 F1472 8 2 REACTION (64-GD-0(A,X)66-DY-155,,SIG) F1472 8 3 DECAY-DATA (66-DY-155,9.9HR,DG,184.56,0.0337,DG,226.92,0.684) F1472 8 4 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 8 5 was calculated as the square root of the sum of the F1472 8 6 squares of the individual uncertainties: F1472 8 7 (ERR-1) uncertainty in determining the efficiency of F1472 8 8 the detector; F1472 8 9 (ERR-2,1.,10.) uncertainty in determining the F1472 8 10 photopeak area; F1472 8 11 (ERR-3) uncertainty in determining the target F1472 8 12 thickness; F1472 8 13 (ERR-4) uncertainty of nuclear data; F1472 8 14 (ERR-5) uncertainty of current value. F1472 8 15 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 8 16 ENDBIB 14 0 F1472 8 17 COMMON 4 3 F1472 8 18 ERR-1 ERR-3 ERR-4 ERR-5 F1472 8 19 PER-CENT PER-CENT PER-CENT PER-CENT F1472 8 20 7. 10. 3. 10. F1472 8 21 ENDCOMMON 3 0 F1472 8 22 DATA 4 17 F1472 8 23 EN EN-ERR DATA ERR-T F1472 8 24 MEV MEV MB MB F1472 8 25 58.9 1.5 183.7 33.5 F1472 8 26 57.1 1.6 231.3 43.9 F1472 8 27 55.2 1.8 249.6 46.6 F1472 8 28 53.3 1.9 166. 98. F1472 8 29 51.3 2.0 209.1 37.7 F1472 8 30 49.3 2.2 169.2 26.8 F1472 8 31 47.5 2.4 165.0 27.8 F1472 8 32 45.4 2.6 139.3 22.6 F1472 8 33 43.5 2.7 136.7 23.1 F1472 8 34 41.2 3.0 70.6 11.7 F1472 8 35 38.4 3.3 46.62 8.92 F1472 8 36 35.3 3.7 21.16 4.25 F1472 8 37 33.0 3.9 12.16 2.13 F1472 8 38 30.0 4.4 5.19 1.17 F1472 8 39 26.8 4.9 0.65 0.14 F1472 8 40 23.2 5.7 0.37 0.10 F1472 8 41 20.3 6.4 0.51 0.12 F1472 8 42 ENDDATA 19 0 F1472 8 43 ENDSUBENT 42 0 F1472 899999 SUBENT F1472009 20230120 F094F1472 9 1 BIB 4 14 F1472 9 2 REACTION (64-GD-0(A,X)66-DY-157,,SIG) F1472 9 3 DECAY-DATA (66-DY-157,8.14HR,DG,182.42,0.0133,DG,326.34,0.93) F1472 9 4 ERR-ANALYS (ERR-T) The uncertainty in the cross section value F1472 9 5 was calculated as the square root of the sum of the F1472 9 6 squares of the individual uncertainties: F1472 9 7 (ERR-1) uncertainty in determining the efficiency of F1472 9 8 the detector; F1472 9 9 (ERR-2,1.,10.) uncertainty in determining the F1472 9 10 photopeak area; F1472 9 11 (ERR-3) uncertainty in determining the target F1472 9 12 thickness; F1472 9 13 (ERR-4) uncertainty of nuclear data; F1472 9 14 (ERR-5) uncertainty of current value. F1472 9 15 STATUS (TABLE) Tbl. 3 from Nucl.Med. Biol., 106-107, 52,2022 F1472 9 16 ENDBIB 14 0 F1472 9 17 COMMON 4 3 F1472 9 18 ERR-1 ERR-3 ERR-4 ERR-5 F1472 9 19 PER-CENT PER-CENT PER-CENT PER-CENT F1472 9 20 7. 10. 3. 10. F1472 9 21 ENDCOMMON 3 0 F1472 9 22 DATA 4 17 F1472 9 23 EN EN-ERR DATA ERR-T F1472 9 24 MEV MEV MB MB F1472 9 25 58.9 1.5 230.6 37.1 F1472 9 26 57.1 1.6 316.5 51.4 F1472 9 27 55.2 1.8 361.7 57.9 F1472 9 28 53.3 1.9 245. 138. F1472 9 29 51.3 2.0 317.8 51.0 F1472 9 30 49.3 2.2 262.2 42.1 F1472 9 31 47.5 2.4 277.2 43.9 F1472 9 32 45.4 2.6 283.9 44.9 F1472 9 33 43.5 2.7 337.9 53.8 F1472 9 34 41.2 3.0 270.9 42.8 F1472 9 35 38.4 3.3 300.7 51.7 F1472 9 36 35.3 3.7 266.1 42.1 F1472 9 37 33.0 3.9 219.5 35.4 F1472 9 38 30.0 4.4 191.4 31.1 F1472 9 39 26.8 4.9 129.9 21.9 F1472 9 40 23.2 5.7 75.5 12.5 F1472 9 41 20.3 6.4 47.2 7.5 F1472 9 42 ENDDATA 19 0 F1472 9 43 ENDSUBENT 42 0 F1472 999999 SUBENT F1472010 20230120 F094F1472 10 1 BIB 5 8 F1472 10 2 REACTION (64-GD-0(A,X)65-TB-155,,TTY,,PHY,DERIV) F1472 10 3 DECAY-DATA (65-TB-155,5.32D,DG,86.55,0.32,DG,105.32,0.251, F1472 10 4 DG,180.08,0.075,DG,262.27,0.053) F1472 10 5 ANALYSIS (INTEF) F1472 10 6 FLAG (1.) With separation of Dy F1472 10 7 (2.) No Dy separation F1472 10 8 STATUS (TABLE) Tbl. 4 from Nucl.Med. Biol., 106-107, 52,2022 F1472 10 9 (DEP,F1472006) Excitation function F1472 10 10 ENDBIB 8 0 F1472 10 11 COMMON 1 3 F1472 10 12 TIME-IRRD F1472 10 13 MIN F1472 10 14 50. F1472 10 15 ENDCOMMON 3 0 F1472 10 16 DATA 3 3 F1472 10 17 EN DATA FLAG F1472 10 18 MEV MBQ/MUAHR NO-DIM F1472 10 19 50. 0.76 1. F1472 10 20 60. 1.98 1. F1472 10 21 60. 2.48 2. F1472 10 22 ENDDATA 5 0 F1472 10 23 ENDSUBENT 22 0 F1472 1099999 ENDENTRY 10 0 F147299999999