ENTRY 22857 20170301 22592285700000001 SUBENT 22857001 20170301 22592285700100001 BIB 17 136 2285700100002 TITLE Nuclear data for production of the therapeutic radio- 2285700100003 nuclides P-32, Cu-64, Cu-67, Sr-89, Y-90 and Sm-153 2285700100004 via the (N,P) reaction: Evaluation of excitation 2285700100005 function and its validation via integral cross-section2285700100006 measurement using a 14-MeV D(Be) neutron source. 2285700100007 AUTHOR (M.AL-Abyad, I.Spahn, S.Sudar, M.Morsy, M.N.H.Comsan, 2285700100008 J.Csikai, S.M.Qaim, H.H.Coenen) 2285700100009 INSTITUTE (2GERJUL) Institut fuer Nuclear Chemie, Forschungs- 2285700100010 zentrum, Juelich. Al-Abyad, Spahn, Sudar, Qaim, 2285700100011 Coenen. Experimental site 2285700100012 (3EGYCAI) Al-Abyad, Morsy, Comsan 2285700100013 (3HUNDEB) Csikai 2285700100014 REFERENCE (J,ARI,64,717,2006) Main reference. Data for S-32(N,P),2285700100015 Zr-90(N,P), Eu-153(N,P) reactions 2285700100016 (J,RCA,92,183,20040105) Data for the Zn-64, Zn-67, 2285700100017 Y-89 (n,p) reactions. 2285700100018 (R,EUR-22794-EN,121,2006) First author - I.Spahn. 2285700100019 Report EUR 22794 EN - Proc. of the enlargement workshop2285700100020 25-28 Oct.2006, Borovets, Bulgaria. Edited by 2285700100021 A.J.M.Plompen. 2285700100022 REL-REF (I,22664001,M.Ibn Majah+,J,ARI,54,655,2001) More 2285700100023 details of experiment. 2285700100024 (M,,K.Kettern+,C,2004SANTA,758,2004) 2285700100025 Data of Reference (J,RCA,92,183,2004) for Y-89(n,p) 2285700100026 reaction were confirmed (Subent .004). 2285700100027 FACILITY (CYCLO,2GERJUL) Variable energy compact cyclotron CV28.2285700100028 INC-SOURCE (D-BE) Deuterons with primary energy 14 MeV impinging 2285700100029 the thick beryllium target 19.7 mm diameter, 1.9 mm 2285700100030 thick, 98% purity embedded into 2 mm thick copper 2285700100031 holder cooled with water. 2285700100032 DETECTOR (HPGE) HPGE-detector (ORTEC) to measure radioactivity 2285700100033 of irradiated monitor foils and Sm-153 2285700100034 METHOD (ACTIV) Activation 2285700100035 (STTA) Stack target irradiation. Each sample was 2285700100036 irradiated simultaneously with a set of AL and Fe 2285700100037 monitor foils attached on both sides of the sample 2285700100038 INC-SPECT -Continuous neutron energy spectrum evaluated using 2285700100039 averaged cross section and the measured activity 2285700100040 of the elements given below. Has two maxima - the 2285700100041 first large at aprx 3 MeV and the second - small at 2285700100042 14 MeV neutron energy. 2285700100043 Maximal flux density occurs at 2.5 - 3.5 MeV neutron 2285700100044 energy. 2285700100045 -Reactions and decay data used for neutron spectrum 2285700100046 evaluation via SULSA code follow: 2285700100047 <28-NI-58(N,P)27-CO-58,,SIG> 2285700100048 <49-IN-115(N,INL)49-IN-115-M,,SIG> 2285700100049 <22-TI-47(N,P)21-SC-47,,SIG> 2285700100050 <26-FE-54(N,P)25-MN-54,,SIG> 2285700100051 <22-TI-46(N,P)21-SC-46,,SIG> 2285700100052 <26-FE-56(N,P)25-MN-56,,SIG> 2285700100053 <13-AL-27(N,A)11-NA-24,,SIG> 2285700100054 <22-TI-48(N,P)21-SC-48,,SIG> 2285700100055 <79-AU-197(N,2N)79-AU-196,,SIG> 2285700100056 <41-NB-93(N,2N)41-NB-92-M,,SIG> 2285700100057 <28-NI-58(N,2N)28-NI-57,,SIG> 2285700100058 The deduced neutron spectrum at o deg 2285700100059 ( digitized values from Fig.7 of ARI,64,717,2006 ; 2285700100060 digitization errors : 2285700100061 energy En scale, MeV - 0.0087 2285700100062 neutron flux F scale, arb.units - 0.000081 2285700100063 quantization errors ( one pixel): 2285700100064 energy En scale, MeV - 0.019 2285700100065 neutron flux F scale, arb.units - 0.00016 ) : 2285700100066 En F En F 2285700100067 0.872 0.04933 8.376 0.01784 2285700100068 1.118 0.05606 8.603 0.01653 2285700100069 1.364 0.06165 8.869 0.01521 2285700100070 1.610 0.06592 9.115 0.01406 2285700100071 1.856 0.06871 9.361 0.01308 2285700100072 2.102 0.07068 9.627 0.01210 2285700100073 2.367 0.07200 9.873 0.01128 2285700100074 2.613 0.07200 10.081 0.01078 2285700100075 2.860 0.07151 10.346 0.01062 2285700100076 3.125 0.07036 10.593 0.01046 2285700100077 3.352 0.06855 10.839 0.01062 2285700100078 3.618 0.06626 11.085 0.01095 2285700100079 3.864 0.06347 11.351 0.01161 2285700100080 4.111 0.06051 11.597 0.01243 2285700100081 4.376 0.05739 11.843 0.01342 2285700100082 4.623 0.05395 12.089 0.01457 2285700100083 4.869 0.05017 12.335 0.01556 2285700100084 5.116 0.04656 12.601 0.01687 2285700100085 5.362 0.04295 12.847 0.01802 2285700100086 5.609 0.03950 13.093 0.01950 2285700100087 5.874 0.03622 13.339 0.02032 2285700100088 6.120 0.03326 13.586 0.02114 2285700100089 6.367 0.03064 13.832 0.02164 2285700100090 6.613 0.02850 14.097 0.02197 2285700100091 6.860 0.02670 14.343 0.02213 2285700100092 7.106 0.02506 14.590 0.02213 2285700100093 7.371 0.02358 14.836 0.02164 2285700100094 7.618 0.02194 15.082 0.02066 2285700100095 7.864 0.02063 15.348 0.01951 2285700100096 8.111 0.01915 15.594 0.01754 2285700100097 DECAY-DATA (27-CO-58-G,70.91D,DG,810.7,0.9944) Thres.en.,MeV 0.4 2285700100098 (49-IN-115-M,4.48HR,DG,336.0,0.4590)Thres.en.,MeV 0.4 2285700100099 (21-SC-47,3.34D,DG,159.0,0.6790) Thres.en.,MeV 1.0 2285700100100 (25-MN-54,312.2D,DG,834.5,0.9997) Thres.en.,MeV 1.5 2285700100101 (21-SC-46-G,83.83D,DG,889.0,0.9997) Thres.en.,MeV 1.8 2285700100102 (25-MN-56,2.57HR,DG,846.0,1.00) Thres.en.,MeV 2.8 2285700100103 (11-NA-24,15.03HR,DG,1369.0,1.00) Thres.en.,MeV 3.2 2285700100104 (21-SC-48,1.82D,DG,983.0,1.00) Thres.en.,MeV 3.2 2285700100105 (79-AU-196-G,6.18D,DG,355.6,0.870) Thres.en.,MeV 8.0 2285700100106 (41-NB-92-M,10.15D,DG,934.0,1.00) Thres.en.,MeV 8.8 2285700100107 (28-NI-57,1.50D,DG,127.2,.166) Thres.en.,MeV 12.4 2285700100108 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2285700100109 (26-FE-56(N,P)25-MN-56,,SIG) The excitation functions 2285700100110 of these monitor reactions were taken from the 2285700100111 International Radiation Dosimetry File (IRDF-2002) and2285700100112 averaged for the standard neutron spectrum, described 2285700100113 above. 2285700100114 DECAY-MON (11-NA-24,15.03HR,DG,1369.,1.0) 2285700100115 (25-MN-56,2.57HR,DG,846.,1.0) 2285700100116 MONIT-REF (,,R,IAEA-TECDOC-1285,2002) Neutron activation library 2285700100117 ERR-ANALYS (ERR-S,,2.) Maximal statistical error 2285700100118 (ERR-1) B- and annihilation radiation decay curve 2285700100119 analysis error 2285700100120 (ERR-2) Gamma counting detector efficiency error 2285700100121 (ERR-3) B- counting detector efficiency error 2285700100122 (ERR-4,,1.) Sample mass maximal error 2285700100123 (ERR-5,,3.) Decay constants maximal error 2285700100124 (ERR-6) Average neutron flux error 2285700100125 (ERR-7) Chemical yield error 2285700100126 STATUS (TABLE) Data from tables of references. 2285700100127 HISTORY (20050321C) S.M./M.M. 2285700100128 (20061012A) BIB-information corrected - SM. 2285700100129 Three new SUBENTS added. Energy EN to EN-DUMMY changed2285700100130 (20080109A) Misprint in EN-DUMMY value was corrected. 2285700100131 Rel-Reference was added. M.M./S.M. 2285700100132 (20080109U) 3rd reference and STATUS information were 2285700100133 added. M.M. 2285700100134 (20100714A) M.M. Parenthesis in MONIT-REF (Subent 001) 2285700100135 and MONITOR (002-004) moved to col 12 2285700100136 (20170301A) M.M. Inc.spectrum data were added. 2285700100137 ERR-ANALYS was corrected according to new rules. 2285700100138 ENDBIB 136 0 2285700100139 COMMON 6 3 2285700100140 EN-DUMMY ERR-1 ERR-2 ERR-3 ERR-6 ERR-7 2285700100141 MEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2285700100142 3. 5. 5. 12. 15. 8. 2285700100143 ENDCOMMON 3 0 2285700100144 ENDSUBENT 143 0 2285700199999 SUBENT 22857002 20170301 22592285700200001 BIB 9 24 2285700200002 REACTION (30-ZN-64(N,P)29-CU-64,,SIG,,SPA) Averaged over the 2285700200003 neutron spectrum of (D-Be) source 2285700200004 METHOD (GSPEC) Gamma-ray-spectroscopy 2285700200005 (CHSEP) modern methods of radiochemical separation of 2285700200006 CU-64 determined radiochemically separation yield was 2285700200007 about 86% for Cu. 2285700200008 DETECTOR (GELI) GE(LI) detector (CANBERRA) for separated 2285700200009 Cu fractions 2285700200010 (IOCH) For annihilation photons of Cu-64 positrons. 2285700200011 Chamber made of 2 mm thick copper 2285700200012 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) 2285700200013 DECAY-DATA (29-CU-64,12.7HR,DG,,0.38) 2285700200014 SAMPLE ZN-O oxide of 99.9% purity. 2285700200015 Material was pressed into a pellet of 20 mm diameter 2285700200016 and 4 mm thickness,put in aluminium capsule. 2285700200017 high purity Al, Fe, Ni foils on both ends of capsule. 2285700200018 sample was placed in 0 degrees direction at 1 cm 2285700200019 distance from neutron source. 2285700200020 ERR-ANALYS (ERR-T) Total uncertainty for measurement of Cu-64 2285700200021 via annihilation radiation 19.% 2285700200022 STATUS (TABLE) Table of RCA,92,183,2004. 2285700200023 Table 1 of EUR-22794-EN,121,2006 2285700200024 Table 3 of ARI,64,717,2006 2285700200025 HISTORY (20061012A) BIB-information updated 2285700200026 ENDBIB 24 0 2285700200027 NOCOMMON 0 0 2285700200028 DATA 2 1 2285700200029 DATA ERR-T 2285700200030 MB MB 2285700200031 132. 25. 2285700200032 ENDDATA 3 0 2285700200033 ENDSUBENT 32 0 2285700299999 SUBENT 22857003 20170301 22592285700300001 BIB 9 22 2285700300002 REACTION (30-ZN-67(N,P)29-CU-67,,SIG,,SPA) Averaged over the 2285700300003 neutron spectrum of (D-Be) source 2285700300004 DETECTOR (GELI) GE(LI) detector (CANBERRA) for separated 2285700300005 Cu fractions 2285700300006 METHOD (GSPEC) Gamma-ray-spectroscopy 2285700300007 (CHSEP) modern methods of radiochemical separation of 2285700300008 CU-67 was determined radiochemically, separation 2285700300009 yield was about 86% for Cu. 2285700300010 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) 2285700300011 DECAY-DATA (29-CU-67,61.9HR,DG,184.6,0.487) 2285700300012 SAMPLE ZN-O oxide of 99.9% purity 2285700300013 Material was pressed into a pellet of 20 mm diameter 2285700300014 and 4 mm thickness,put in aluminum capsule. 2285700300015 high purity Al, Fe, Ni foils on both ends of capsule. 2285700300016 sample was placed in 0 degrees direction at 1 cm 2285700300017 distance from neutron source. 2285700300018 ERR-ANALYS (ERR-T) Total uncertainty for measurement of Cu-67 2285700300019 via gamma-ray spectrometry nd-contribution - 17.% . 2285700300020 STATUS (TABLE) Table of RCA,92,183,2004. 2285700300021 Table 1 of EUR-22794-EN,121,2006 2285700300022 Table 3 of ARI,64,717,2006 2285700300023 HISTORY (20061012A) BIB-information updated 2285700300024 ENDBIB 22 0 2285700300025 NOCOMMON 0 0 2285700300026 DATA 2 1 2285700300027 DATA ERR-T 2285700300028 MB MB 2285700300029 5.13 0.87 2285700300030 ENDDATA 3 0 2285700300031 ENDSUBENT 30 0 2285700399999 SUBENT 22857004 20170301 22592285700400001 BIB 9 23 2285700400002 REACTION (39-Y-89(N,P)38-SR-89,,SIG,,SPA) Averaged over the 2285700400003 neutron spectrum of (D-Be) source 2285700400004 METHOD (GSPEC) Gamma-ray-spectroscopy 2285700400005 (CHSEP) modern methods of radiochemical separation of 2285700400006 SR-89 determined radiochemically. Sr-89 chemical 2285700400007 yield 40% was determined via neutron activation 2285700400008 analysis. 2285700400009 DETECTOR (PROPC) anticoincidence gas flow proportional counter 2285700400010 To determine Sr-89 radioactivity 2285700400011 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) 2285700400012 DECAY-DATA (38-SR-89,50.5D,B-) 2285700400013 SAMPLE Y2-O3 oxide of 99.99% purity. 2285700400014 Material was pressed into a pellet of 20 mm diameter 2285700400015 and 4 mm thickness, put in aluminum capsule. 2285700400016 high purity Al, Fe, Ni foils on both ends of capsule. 2285700400017 sample was placed in 0 degrees direction at 1 cm 2285700400018 distance from neutron source. 2285700400019 ERR-ANALYS (ERR-T) Total uncertainty for measurement of Sr-89 2285700400020 via B- counting 22.% 2285700400021 STATUS (TABLE) Table of RCA,92,183,2004. 2285700400022 Table 1 of EUR-22794-EN,121,2006 2285700400023 Table 3 of ARI,64,717,2006 2285700400024 HISTORY (20061012A) BIB-information updated 2285700400025 ENDBIB 23 0 2285700400026 NOCOMMON 0 0 2285700400027 DATA 2 1 2285700400028 DATA ERR-T 2285700400029 MB MB 2285700400030 0.91 0.20 2285700400031 ENDDATA 3 0 2285700400032 ENDSUBENT 31 0 2285700499999 SUBENT 22857005 20170301 22592285700500001 BIB 7 10 2285700500002 REACTION (16-S-32(N,P)15-P-32,,SIG,,SPA) Averaged over the 2285700500003 neutron spectrum of (D-Be) source 2285700500004 DETECTOR (PROPC) A well calibrated gas-flow proportional counter2285700500005 DECAY-DATA (15-P-32,14.3D,B-,1.7E+03) 2285700500006 SAMPLE High-pure materials - S of natural isotopic 2285700500007 composition were prepared 0.05-0.3-mm thick. 2285700500008 ERR-ANALYS (ERR-T) Total uncertainty 2285700500009 STATUS (TABLE) Tables 2,3 of ARI,64,717,2006. 2285700500010 Table 1 of EUR-22794-EN,121,2006 2285700500011 HISTORY (20061012C) SM 2285700500012 ENDBIB 10 0 2285700500013 NOCOMMON 0 0 2285700500014 DATA 2 1 2285700500015 DATA ERR-T 2285700500016 MB MB 2285700500017 152. 27. 2285700500018 ENDDATA 3 0 2285700500019 ENDSUBENT 18 0 2285700599999 SUBENT 22857006 20170301 22592285700600001 BIB 8 15 2285700600002 REACTION (40-ZR-90(N,P)39-Y-90,,SIG,,SPA) Averaged over the 2285700600003 neutron spectrum of (D-Be) source 2285700600004 DETECTOR (PROPC) A well calibrated gas-flow proportional counter2285700600005 DECAY-DATA (39-Y-90-G,64.8HR,B-,2.3E+03) 2285700600006 SAMPLE High purity materials Zr-O2 of natural isotopic 2285700600007 composition were prepared 0.05-0.3-mm thick. 2285700600008 COMMENT "S.M.Qaim (2017-05-04): 2285700600009 The counting was done after complete decay of the 2285700600010 3.2 hr isomer." 2285700600011 via N.Otsuka, NDS,IAEA . 2285700600012 ERR-ANALYS (ERR-T) Total uncertainty 2285700600013 STATUS (TABLE) Tables 2,3 of ARI,64,717,2006. 2285700600014 Table 1 of EUR-22794-EN,121,2006 2285700600015 HISTORY (20061012C) SM 2285700600016 (20170504A) -G was deleted from SF4, COMMENT was added.2285700600017 ENDBIB 15 0 2285700600018 NOCOMMON 0 0 2285700600019 DATA 2 1 2285700600020 DATA ERR-T 2285700600021 MB MB 2285700600022 2.7 0.50 2285700600023 ENDDATA 3 0 2285700600024 ENDSUBENT 23 0 2285700699999 SUBENT 22857007 20170301 22592285700700001 BIB 6 9 2285700700002 REACTION (63-EU-153(N,P)62-SM-153,,SIG,,SPA) Averaged over the 2285700700003 neutron spectrum of (D-Be) source 2285700700004 DECAY-DATA (62-SM-153,46.3HR,DG,103.18,0.283) 2285700700005 SAMPLE High purity Eu2-O3 of natural isotopic composition 2285700700006 were prepared 0.05-0.3-mm thick. 2285700700007 ERR-ANALYS (ERR-T) Total uncertainty 2285700700008 STATUS (TABLE) Tables 2,3 of ARI,64,717,2006. 2285700700009 Table 1 of EUR-22794-EN,121,2006 2285700700010 HISTORY (20061012C) SM 2285700700011 ENDBIB 9 0 2285700700012 NOCOMMON 0 0 2285700700013 DATA 2 1 2285700700014 DATA ERR-T 2285700700015 MB MB 2285700700016 0.26 0.04 2285700700017 ENDDATA 3 0 2285700700018 ENDSUBENT 17 0 2285700799999 ENDENTRY 7 0 2285799999999