ENTRY D4198 20120502 D083D419800000001 SUBENT D4198001 20120502 D083D419800100001 BIB 15 76 D419800100002 TITLE Production of the therapeutic radionuclides 193mPt and D419800100003 195mPt with high specific activity via alfa-particle- D419800100004 induced reactions on 192Os D419800100005 AUTHOR (K.Hilgers, H.H.Coenen, S.M.Qaim) D419800100006 INSTITUTE (2GERJUL) D419800100007 REFERENCE (J,ARI,66,545,2008) D419800100008 FACILITY (CYCLO,2GERJUL) CV-28 compact cyclotron D419800100009 SAMPLE Thin osmium samples were prepared by electrolytic D419800100010 deposition of enriched 192Os (chemical purity: 99.9+%,D419800100011 isotopic composition: 84.5% 192Os, 15.2% 190Os, 0.3% D419800100012 189Os) on 25 micron thick Ni foils (99.9% pure) from D419800100013 an alkaline solution. D419800100014 The absence of all oxides could be confirmed. D419800100015 The osmium deposit was covered by a 10 micron thick Al D419800100016 foil. Monitor foils: Ti and Cu (both >99.6% pure) D419800100017 with thicknesses of 10 and 25 micron. D419800100018 METHOD (STTA,ACTIV,EXTB,GSPEC) D419800100019 Several stacks consisting of a few 192Os samples and D419800100020 thin Ti and Cu monitor foils were irradiated. D419800100021 Primary alpha energy: 28 MeV. D419800100022 The beam flux was measured by charge integration as D419800100023 well as via monitor reactions. D419800100024 A chemical separation procedure was applied to isolate D419800100025 the radioplatinum from the background activity, thus D419800100026 enabling the preparation of a clean and thin source D419800100027 suitable for X-ray counting. D419800100028 The yield of radiochemical separation was between 60% D419800100029 and 90%. The gamma-ray analysis also showed that the D419800100030 contamination of radioplatinum by non-isotopic D419800100031 radionuclidic impurities (56,58Co, 65Zn, etc.) was D419800100032 <0.01%. D419800100033 Spectra were recorded several times to check the half- D419800100034 life of the products. D419800100035 DETECTOR (HPGE) D419800100036 An HPGe detector with a thin Be-window (a special D419800100037 detector for low-energy gamma-rays) was used. D419800100038 The sample to detector distance was 3 cm. D419800100039 For measuring the activity of each monitor foil as D419800100040 well as for determining the radiocontaminants in each D419800100041 radioplatinum sample, standard gamma-ray spectrometry D419800100042 using a large-size HPGe detector was applied. D419800100043 The sample to detector distance was between 10 and D419800100044 50 cm in the case of monitor foils, and between 3 and D419800100045 5 cm while measuring the chemically separated D419800100046 radioplatinum samples. D419800100047 MONITOR (22-TI-0(A,X)24-CR-51,,SIG) D419800100048 (29-CU-0(A,X)31-GA-66,,SIG) D419800100049 (29-CU-0(A,X)31-GA-67,,SIG) D419800100050 (29-CU-0(A,X)30-ZN-65,,SIG) D419800100051 MONIT-REF (,F.Tarkanyi+,R,IAEA-TECDOC-1211,2001) Chapter 4 D419800100052 REL-REF (N,,C.F.Williamson+,R,CEA-R-3042,1966) D419800100053 The calculation of the energy degradation within each D419800100054 stack was based on the method of Williamson et al. D419800100055 (R,,R.B.Firestone+,B,FIRESTONE,,1996) D419800100056 Decay data were taken (CDROM-Edition, Ver.1.0, 1996) D419800100057 ERR-ANALYS (EN-ERR) The uncertainty in the primary particle D419800100058 energy amounted to 0.2 MeV. D419800100059 The uncertainty in the energy effective at each foil D419800100060 increased with increasing number of foils. D419800100061 (ERR-T) Total uncertainty (12-18%). D419800100062 Uncertainties and their magnitudes in cross-section D419800100063 measurements: D419800100064 * Uncertainty in projectile energy effective in a D419800100065 sample 0.2-0.8 MeV D419800100066 (ERR-1) number of target nuclei (2%) D419800100067 (ERR-2) target uniformity (5%) D419800100068 (ERR-3) chemical yield determination (3%) D419800100069 (ERR-4) decay data (5%) D419800100070 (ERR-5,4.,7.) efficiency of the detector (4-7%) D419800100071 (ERR-6,2.,10.) peak area analysis (2-10%) D419800100072 (ERR-7,9.,12.) monitor reaction cross-section (9-12%) D419800100073 ADD-RES (TTY-C) On the basis of the new experimental cross D419800100074 sections integral yields were calculated. D419800100075 STATUS (APRVD) S.Takacs, 2008.04.30. D419800100076 HISTORY (20080415C) KB D419800100077 (20120502U) On. ERR-ANALYS: Coded information added. D419800100078 ENDBIB 76 0 D419800100079 COMMON 4 3 D419800100080 ERR-1 ERR-2 ERR-3 ERR-4 D419800100081 PER-CENT PER-CENT PER-CENT PER-CENT D419800100082 2. 5. 3. 5. D419800100083 ENDCOMMON 3 0 D419800100084 ENDSUBENT 83 0 D419800199999 SUBENT D4198002 20080415 D060D419800200001 BIB 4 11 D419800200002 REACTION (76-OS-192(A,N)78-PT-195-M,,SIG) D419800200003 DECAY-DATA (78-PT-195-M,4.03D,XR,66.8,0.390, D419800200004 DG,98.9,0.114) D419800200005 METHOD The activity of the radiochemically separated 195mPt D419800200006 was determined using a gamma-ray at 98.9 keV and also D419800200007 a K-alpha X-ray of energy 66.8 keV. The threshold of D419800200008 the 192Os(a,3n)193mPt reaction lies at about 23 MeV. D419800200009 For the calculation of the cross-section of the D419800200010 192Os(a,n)195mPt reaction above 23 MeV only the D419800200011 gamma-ray was used. D419800200012 STATUS (TABLE) Data were taken from Table 3 of the Ref. D419800200013 ENDBIB 11 0 D419800200014 NOCOMMON 0 0 D419800200015 DATA 4 12 D419800200016 EN EN-ERR DATA ERR-T D419800200017 MEV MEV MB MB D419800200018 27.5 0.2 1.5 0.2 D419800200019 26.5 0.2 3.3 0.5 D419800200020 26.0 0.3 1.4 0.2 D419800200021 25.0 0.3 2.8 0.4 D419800200022 23.5 0.4 3.3 0.5 D419800200023 22.1 0.5 4.4 0.7 D419800200024 21.3 0.5 2.9 0.4 D419800200025 20.0 0.6 2.4 0.4 D419800200026 19.2 0.6 3.7 0.6 D419800200027 18.1 0.7 2.1 0.3 D419800200028 17.3 0.8 1.7 0.2 D419800200029 15.9 0.9 0.6 0.1 D419800200030 ENDDATA 14 0 D419800200031 ENDSUBENT 30 0 D419800299999 SUBENT D4198003 20080415 D060D419800300001 BIB 4 18 D419800300002 REACTION (76-OS-192(A,3N)78-PT-193-M,,SIG) D419800300003 DECAY-DATA (78-PT-193-M,4.33D,XR,66.8,0.074) D419800300004 METHOD The K-alpha X-ray line at 66.8 keV was used to D419800300005 determine the activity of 193mPt, after subtracting D419800300006 the contribution of 195mPt. D419800300007 It should be pointed out that at 23.5 MeV, besides D419800300008 the reaction 192Os(a,3n)193mPt the reaction D419800300009 190Os(a,n)193mPt may also contribute to the formation D419800300010 of 193mPt. However, considering the low abundance of D419800300011 190Os in the enriched 192Os sample and assuming the D419800300012 cross-section of the 190Os(a,n) reaction to be similar D419800300013 to that of the 192Os(a,n) reaction, the contribution ofD419800300014 the 190Os(a,n) reaction to the formation of 193mPt was D419800300015 estimated to be <10% of that of the 192Os(a,3n) D419800300016 process, i.e. within the limits of experimental D419800300017 uncertainties. At energies >24 MeV this contribution D419800300018 becomes negligible. D419800300019 STATUS (TABLE) Data were taken from Table 3 of the Ref. D419800300020 ENDBIB 18 0 D419800300021 NOCOMMON 0 0 D419800300022 DATA 4 7 D419800300023 EN EN-ERR DATA ERR-T D419800300024 MEV MEV MB MB D419800300025 27.5 0.2 197. 30. D419800300026 26.5 0.2 129. 19. D419800300027 26.3 0.2 160. 24. D419800300028 26.0 0.3 43. 6. D419800300029 25.0 0.3 23. 4. D419800300030 24.8 0.3 27. 4. D419800300031 23.5 0.4 7. 1. D419800300032 ENDDATA 9 0 D419800300033 ENDSUBENT 32 0 D419800399999 ENDENTRY 3 0 D419899999999