Possibilities of proton-activation analysis for determining the content of elements from short-lived radionuclides

Muminov, V.A.; Mukhammedov, S.; Vasidov, A.

doi:10.1007/bf01121617

Cited by 6 publications

(12 citation statements)

References 11 publications

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“…They are also shown in Figs. 2-7 as a function of the proton energy, together with the corresponding literature data [7,[23][24][25][26][27][28][29]. For direct comparison the literature cross section data measured on enriched target materials given in the figures were converted to the natural abundance of the respective chromium isotope (see Table 3).…”

Section: Present Literature and New Experimental Resultsmentioning

confidence: 99%

“…Some yields found in the literature are also listed in Table 4 [28,33,34]. These were arithmetically converted into the saturation thick target yields in Bq/μA for comparison.…”

Section: Integral Yieldsmentioning

confidence: 99%

“…This is only 38.5% of our experimental results and 36.6% of our theoretical calculations. Other reported thick target yields are either covering a too narrow (12 MeV to beam stop [28]) or a too large energy region (22 MeV to threshold [34]), where more radioactive impurities (e.g. 48,49,51 Cr) are produced.…”

Section: Integral Yieldsmentioning

confidence: 99%

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Cross-section measurements for the formation of manganese-52 and its isolation with a non-hazardous eluent

et al. 2013

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Nuclear reaction / Cross section / Thick target yield / Integral yield / Separation of positron emitter52 Mn / Ion exchange chromatography Summary. With respect to the production of no-carrieradded 52 Mn nuclear reactions on natural chromium were investigated. Cross sections of the reactions nat Cr( p, x) 48 V, 48,49,51 Cr, 52g,m Mn were determined in the proton energy range of 7.6 to 45 MeV. Additionally, production yields of 52g,m Mn and 51 Cr were measured in the energy range from 8.2 to 16.9 MeV and therefrom the calculated saturation thick target yields were obtained as (2.55 ± 0.31), (6.96 ± 0.57), and (1.53 ± 0.15) GBq/μA, respectively.For in vivo applications like PET, low toxicity is critical and sufficient activity of a radiolabelled compound mandatory. Thus, additional purification steps after separation of radionuclides and target materials have to be avoided. However, no isolation procedure has been reported in the literature so far where radiomanganese is directly obtained in a nonhazardous solution. Therefore a new separation procedure was developed utilizing the cation-exchange resin DOWEX 50W×8 (H + -form). 52g Mn was quantitatively isolated from "bulk" chromium after 3 to 4 h in non-hazardous 0.067 M ammonium citrate solution. Up to 99% of 52g Mn activity was harvested within 10 to 15 mL eluent solution with no measureable 51 Cr impurities.

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Section: Present Literature and New Experimental Resultsmentioning

confidence: 99%

“…Some yields found in the literature are also listed in Table 4 [28,33,34]. These were arithmetically converted into the saturation thick target yields in Bq/μA for comparison.…”

Section: Integral Yieldsmentioning

confidence: 99%

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Cross-section measurements for the formation of manganese-52 and its isolation with a non-hazardous eluent

et al. 2013

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“…Additional experiments were performed by various CRP participants as crucial support in defining the excitation functions of the 45 Sc(d,3n) 44 Ti, nat Ni(p,x) 52 Fe, 55 Mn(p,4n) 52 Fe, 50 Cr(α,2n) 52 Fe, 58 Ni(p,α) 55 Co, 61 Ni(p,n) 61 Cu, 60 Ni(d,n) 61 Cu, nat Ga(p,x) 68 Ge, nat Ge(p,xn) 72 As, nat Ge(d,xn) 72 As, 89 Y(d,2n) 89 Zr, 93 Nb(p,x) 90 Nb, 92 Mo(α,x) 94m Tc , 110 Cd(p,n) 110m In, 107 Ag(α,n) 110m In, nat Sb(p,xn) 118 Te and 141 Pr(d,3n) 140 Nd reactions. Details of these studies have been reported individually and separately in other dedicated publications (see references for specific reactions given below).…”

Section: New Crp Measurementsmentioning

confidence: 99%

Recommended nuclear data for medical radioisotope production: diagnostic positron emitters

Tárkányi

Ignatyuk

Hermanne

et al. 2019

J Radioanal Nucl Chem

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An IAEA coordinated research project that began in 2012 and ended in 2016 was primarily dedicated to the compilation, evaluation and recommendation of cross-section data for the production of medical radionuclides. One significant part of this work focused on diagnostic positron emitters. These particular studies consist of 69 reactions for direct and indirect or generator production of 44 Sc(44 Ti), 52m Mn(52 Fe), 52g Mn, 55 Co, 61 Cu, 62 Cu(62 Zn), 66 Ga, 68 Ga(68 Ge), 72 As(72 Se), 73 Se, 76 Br, 82 Rb(82 Sr), 82m Rb, 86 Y, 89 Zr, 90 Nb, 94m Tc, 110m In(110 Sn), 118 Sb(118 Te), 120 I, 122 I(122 Xe), 128 Cs(128 Ba), and 140 Pr(140 Nd) medical radionuclides. The resulting reference cross-section data were obtained from Padé fits to selected and corrected experimental data, and integral thick target yields were subsequently deduced. Uncertainties in the fitted results were estimated via a Padé least-squares method with the addition of a 4% assessed systematic uncertainty. Experimental data were also compared with theoretical predictions available from the TENDL-2015 and TENDL-2017 libraries. All of the numerical reference cross-section data with their corresponding uncertainties and deduced integral thick target yields are available on-line at the IAEA-NDS medical portal www-nds.iaea.org/medic alpor tal and also at the IAEA-NDS web page www-nds.iaea.org/ medic al/posit ron_emitt ers.html.

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“…Geiger-Müller counter 40-ZR-96(P,N)41-NB-96,SIG, 15 40-ZR-92(P,N)41-NB-92,SIG, 10 40-ZR-91(P,N)41-NB-91-M,SIG, 12 2.73-6.67 3.5-6.67 3.5-6.66 (Blosser and Handley, 1955) (Muminov et al, 1980) nat Zr cyclotron no chemical separation Ge(Li) 40-ZR-0(P,N)41-NB-90-M,TTY, 3 9-11 (Dmitriev and Molin, 1981) nat Zr cyclotron single target (Kuzmenko et al, 1987) nat Zr cyclotron stacked foil Faraday cup γ-Ge(Li) 40-ZR-90(P,N)41-NB-90-G,SIG, 1 40-ZR-0(P,X)40-ZR-89,CUM,SIG, 1 40-ZR-0(P,X)39-Y-87,SIG, 1 40-ZR-0(P,X)39-Y-86,SIG, 1 17 19 19 28 (Skakun et al, 1987) 90 Zr 92 Zr 96 Zr LINACsingle foil target Faraday cup γ-Ge(Li) 40-ZR-90(P,N)41-NB-90-M,,SIG, 4 40-ZR-90(P,N)41-NB-90-G,SIG, 3 40-ZR-90(P,N)41-NB-90,SIG, 3 40-ZR-92(P,N)41-NB-92-M,SIG,10 40-ZR-96(P,N)41-NB-96,SIG, 11 7.5-9 8-9 8-9 4.5-94-9 (Gorpinich et al, 1988) nat Zr cyclotron stacked foil Faraday cup γ-Ge(Li) 40-ZR-0(P,X)37-RB-82-M,SIG,EXP, 18 40-ZR-0(P,X)37-RB-83, SIG,EXP,24 40-ZR-0(P,X)37-RB-84,SIG,EXP, 14 43.9-68 35-68 47.5-68 (Nickles, 1991) nat Zr cyclotron Faraday cup γ-Ge(Li) 40-ZR-90(P,N)41-NB-90, TTY, 1 40-ZR-92(P,N)41-NB-92-M,TTY, 1 40-ZR-96(P,N)41-NB-96,TTY, 1 111111 nat Zr cyclotron 27 Al(p,x) 24…”

Section: Acknowledgementsmentioning

confidence: 99%

New activation cross section data on longer lived radio-nuclei produced in proton induced nuclear reaction on zirconium

Tárkányi

Ditrói

Takács

et al. 2015

Applied Radiation and Isotopes

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In the frame of a systematic study of charged particle production routes of medically relevant radionuclei, the excitation function for indirect production of 178m Ta through nat Hf(α,xn) 178−178m Ta nuclear reaction was measured for the first time up to 40 MeV. In parallel, the side reactions nat Hf(α,x) 179,177,176,175 W, 183,182,178g,177,176,175 Ta, 179m,177m,175 Hf were also assessed. Stacked foil irradiation technique and γ-ray spectrometry were used. New experimental cross section data for the nat Ta(d,xn) 178 W reaction are also reported up to 40 MeV. The measured excitation functions are compared with the results of the ALICE-IPPE, and EMPIRE nuclear reaction model codes and with the TALYS 1.4 based data in the TENDL-2013 library. The thick target yields were deduced and compared with yields of other charged particle ((p,4n), (d,5n) and ( 3 He,x)) production routes for 178 W.

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Possibilities of proton-activation analysis for determining the content of elements from short-lived radionuclides

Cited by 6 publications

References 11 publications

Cross-section measurements for the formation of manganese-52 and its isolation with a non-hazardous eluent

Cross-section measurements for the formation of manganese-52 and its isolation with a non-hazardous eluent

Recommended nuclear data for medical radioisotope production: diagnostic positron emitters

New activation cross section data on longer lived radio-nuclei produced in proton induced nuclear reaction on zirconium

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