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