Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator

Radioactive isotopes of palladium (¹⁰³Pd) and rhenium (¹⁸⁶Re and ¹⁸⁸Re) have found wide use in nuclear medicine. The present report deals with the conditions for their production by a photonuclear method at an electron accelerator. Studies have been made into the channels of target isotope/attendant...

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Published in:Вопросы атомной науки и техники
Date:2013
Main Authors: Dikiy, N.P., Kushnir, V.A., Lyashko, Yu.V., Mitrochenko, V.V., Perezhogin, S.A., Rogov, Yu.V., Tenishev, A.Eh., Torgovkin, A.V., Uvarov, V.L., Shevchenko, V.A., Shlyakhov, I.N., Shramenko, B.I.
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Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2013
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Online Access:https://nasplib.isofts.kiev.ua/handle/123456789/112093
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Journal Title:Digital Library of Periodicals of National Academy of Sciences of Ukraine
Cite this:Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator / N.P. Dikiy, V.A. Kushnir, Yu.V. Lyashko, V.V. Mitrochenko, S.A. Perezhogin, Yu.V. Rogov, A.Eh. Tenishev, A.V. Torgovkin, V.L. Uvarov, V.A. Shevchenko, I.N. Shlyakhov, B.I. Shramenko // Вопросы атомной науки и техники. — 2013. — № 6. — С. 196-200. — Бібліогр.: 13 назв. — англ.

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Digital Library of Periodicals of National Academy of Sciences of Ukraine
_version_ 1860085353679945728
author Dikiy, N.P.
Kushnir, V.A.
Lyashko, Yu.V.
Mitrochenko, V.V.
Perezhogin, S.A.
Rogov, Yu.V.
Tenishev, A.Eh.
Torgovkin, A.V.
Uvarov, V.L.
Shevchenko, V.A.
Shlyakhov, I.N.
Shramenko, B.I.
author_facet Dikiy, N.P.
Kushnir, V.A.
Lyashko, Yu.V.
Mitrochenko, V.V.
Perezhogin, S.A.
Rogov, Yu.V.
Tenishev, A.Eh.
Torgovkin, A.V.
Uvarov, V.L.
Shevchenko, V.A.
Shlyakhov, I.N.
Shramenko, B.I.
citation_txt Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator / N.P. Dikiy, V.A. Kushnir, Yu.V. Lyashko, V.V. Mitrochenko, S.A. Perezhogin, Yu.V. Rogov, A.Eh. Tenishev, A.V. Torgovkin, V.L. Uvarov, V.A. Shevchenko, I.N. Shlyakhov, B.I. Shramenko // Вопросы атомной науки и техники. — 2013. — № 6. — С. 196-200. — Бібліогр.: 13 назв. — англ.
collection DSpace DC
container_title Вопросы атомной науки и техники
description Radioactive isotopes of palladium (¹⁰³Pd) and rhenium (¹⁸⁶Re and ¹⁸⁸Re) have found wide use in nuclear medicine. The present report deals with the conditions for their production by a photonuclear method at an electron accelerator. Studies have been made into the channels of target isotope/attendant impurity production as palladium and rhenium targets of natural isotopic composition were exposed to a mixed flux of X-ray (bremsstrahlung) with end-point energy of 40 MeV and photoneutrons. By placing a bremsstrahlung converter and the target inside a neutron moderator, data have been obtained for the effect of photoneutron spectrum on the isotope yield. The simulation technique has been used to investigate the photonuclear yield of target isotopes and major impurities as function of electron energy. Радіоактивні ізотопи паладію (¹⁰³Pd) та ренію (¹⁸⁶Re і ¹⁸⁸Re) широко використовуються в ядерній медицині. Вивчаються умови їх отримання фотоядерним методом на прискорювачі електронів. Досліджено канали напрацювання цільових ізотопів і домішок при опромінюванні мішеней з паладію і ренію природного ізотопного складу змішаним потоком гальмівного випромінювання з граничною енергією 40 МеВ і фотонейтронів. Шляхом розміщення конвертера гальмівного випромінювання і мішені усередині модератора нейтронів отримано дані щодо впливу спектра фотонейтронів на вихід ізотопів. Методом моделювання вивчена також залежність фотоядерного виходу цільових ізотопів і основних домішок від енергії електронів. Радиоактивные изотопы палладия (¹⁰³Pd) и рения (¹⁸⁶Re и ¹⁸⁸Re) широко используются в ядерной медицине. Изучаются условия их получения фотоядерным методом на ускорителе электронов. Исследованы каналы наработки целевых изотопов и примесей при облучении мишеней из палладия и рения природного изотопного состава смешанным потоком тормозного излучения с граничной энергией 40 МэВ и фотонейтронов. Путем размещения конвертера тормозного излучения и мишени внутри модератора нейтронов получены данные по влиянию спектра фотонейтронов на выход изотопов. Методом моделирования изучена также зависимость фотоядерного выхода целевых изотопов и основных примесей от энергии электронов.
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fulltext ISSN 1562-6016. ВАНТ. 2013. №6(88) 196 Pd AND Re ISOTOPE PRODUCTION IN THE FIELD OF MIXED X,n-RADIATION OF ELECTRON ACCELERATOR N.P. Dikiy, V.A. Kushnir, Yu.V. Lyashko, V.V. Mitrochenko, S.A. Perezhogin, Yu.V. Rogov, A.Eh. Tenishev, A.V. Torgovkin, V.L. Uvarov, V.A. Shevchenko, I.N. Shlyakhov, B.I. Shramenko National Science Center “Kharkov Institute of Physics and Technology”, Kharkov, Ukraine E-mail: uvarov@kipt.kharkov.ua Radioactive isotopes of palladium (103Pd) and rhenium (186Re and 188Re) have found wide use in nuclear medi- cine. The present report deals with the conditions for their production by a photonuclear method at an electron ac- celerator. Studies have been made into the channels of target isotope/attendant impurity production as palladium and rhenium targets of natural isotopic composition were exposed to a mixed flux of X-ray (bremsstrahlung) with end- point energy of 40 MeV and photoneutrons. By placing a bremsstrahlung converter and the target inside a neutron moderator, data have been obtained for the effect of photoneutron spectrum on the isotope yield. The simulation technique has been used to investigate the photonuclear yield of target isotopes and major impurities as function of electron energy. PACS: 07.85.-m, 81.40wx,87.53-j,87.53Wz INTRODUCTION Radioactive sources based on the isotopes 103Pd (Ex~20 keV; Т1/2=16.9 days), 186Re (Eβ=346.7 keV; Eγ=137.2 keV; Т1/2= 89.2 hours) and 188Re (Eβ=764.3 keV; Eγ=155.0 keV; Т1/2= 17 hours) are used in current medicine for brachytherapy. Until recently, a common practice for 103Pd produc- tion has been to use the reactor technique, which con- sisted in neutron irradiation of palladium targets en- riched in the 102Pd isotope [1], and also, to employ a cyclotron technology for carrier-free production of the target isotope [2]. The market demand for 103Pd is so great that in the USA only, its production is provided by more than 10 cyclotrons. As regards 186Re isotope sources, they are produced at reactors through thermal neutron irradiation of either rhenium powder enriched in the 185Re isotope [1] or a natural rhenium wire [3]. Attempts of carrier-free pro- duction of the 186Re isotope with the use of a cyclotron have also been made [4]. 188Re is generally obtained as a result of decay of the generating 188W isotope, which is produced in high-flux reactors through the double neu- tron capture by the tungsten target enriched in the 186W isotope [1]. In view of the tendency to gradually abandon the re- actor technologies [5], and also, considering a high cost of cyclotron-produced isotopes, it appears of interest to investigate the conditions of isotope production at rela- tively inexpensive and ecologically safe electron accel- erators. 1. PRINCIPAL REACTIONS Natural palladium presents a mixture of 6 stable iso- topes: 102Pd (1.02%), 104Pd (11.14%), 105Pd (22.33%), 106Pd (27.23%), 108Pd (26.46%) and 110Pd (11.72%). 103Pd can be generated in the field of bremsstrahlung radiation at an electron accelerator due to the reaction 104Pd(γ, n)103Pd. To provide a sufficient flux of brems- strahlung photons in the giant resonance region, the electron energy must range between 35 and 40 MeV. In this case, there arises one more photonuclear channel of desired isotope generation, viz., 105Pd(γ, 2n)103Pd. Be- sides, the process of electron radiation conversion into bremsstrahlung is accompanied by generation of photo- neutrons (e.g., see Ref. [6]). These may give rise to the 102Pd(n, γ)103Pd reaction, too. Natural rhenium consists of two isotopes: 185Re (37.4 %) and 187Re (62.6%). To generate 186Re at an electron accelerator, the reactions 187Re(γ, n)186Re and 185Re(n, γ)186Re can be used. Under the action of photo- neutrons, natural rhenium can also yield 188Re through the 187Re(n, γ)188Re reaction. It is known that the neutron radiative-capture cross- sections in the thermal region increase by one order of value or more. Therefore, for simultaneous engaging the photonuclear and neutron-capture channels, it has been suggested that the bremsstrahlung converter and the isotopic target should be placed inside the neutron mod- erator [7]. 2. EXPERIMENT 2.1. For measuring the isotope yields during expo- sure of targets to a mixed X,n-radiation with and with- out the neutron moderator, an output device has been developed, the schematic of which is presented in Fig. 1. The device includes an aluminum tube 1, which is axially symmetric to the electron beam axis of the accelerator A and accommodates the bremsstrahlung converter C and the target T. The converter consists of four tantalum plates, each 1 mm thick and 30 mm in diameter, separated by same-size air gaps to provide cooling. The target includes the enclosed in aluminum holder 3 aluminum locking discs 4 and 8, each 20 mm in diameter and 3 mm thick. The discs are separated by a 0.1 mm thick molybdenum foil-monitor 5, and a 3 mm thick aluminum spacer having a cell of diameter 10 mm, where the isotopic targets 7 were located. All the targets, except rhenium, presented foil frag- ments of maximum size no more than 5 mm. The rheni- um powder was placed in an aluminum thin-walled cap- sule with an inside diameter 8 mm, and 4 mm in height. 2.2. The fluence of bremsstrahlung photons on the isotopic targets was controlled against the yield of the reference reactions in the foil-monitor 5. Natural mo- lybdenum comprises seven stable isotopes, including 92Mo (14.84%), 98Mo (24.13%) and 100Mo (9.63%). The photon fluence can be estimated against the 90Мо mailto:uvarov@kipt.kharkov.ua ISSN 1562-6016. ВАНТ. 2013. №6(88) 197 (Т1/2=5.7 hours) yield by the 92Мо(γ, 2n)90Mo reaction, because 90Mo can be generated only in this channel. In turn, the isotope 99Mo (T1/2= 66.02 hours) can be gener- ated in the two reactions at once: 100Мо(γ, n)99Мо and 98Мо(n, γ)99Мо. So the comparison between the 90Mo and 99Mo yields, normalized to the electron beam charge on the converter, enables one to estimate the contribu- tion of each of the channels. To determine the profile of the high-energy photon flux, at the converter output a 0.1 mm thick tin-foil 9, measuring 40×40 mm, was placed, which was activated together with the isotope target. The profile of the photon flux was reconstructed by measuring the 2D-distribution of the foil 9 surface activity using a gamma-scanner [8]. 2.3. To measure the isotope yield as a result of a combined action of the bremsstrahlung and moderated photoneutrons, the system with the converter and the target was arranged inside the moderator M. The de- tailed description of the latter can be found in Ref. [7]. In this case, at point 10 of the output device one more isotopic target was placed so that the distance from the target to the beam axis corresponded to the distance from the target 7 to the converter. Each target comprised samples of palladium, rhenium and gold. The latter were used as activation detectors. In this way, the target 7 experienced the action of a mixed flux of brems- strahlung and soft photoneutrons, whereas the target 10 was exposed mostly to neutrons. A 1 2 3 4 e- 5 400 360 ∅ 30 0 ∅ 60C T 6 7 8 M 910 Fig. 1. Schematic of output device 2.4. The targets were irradiated at the NSC KIPT ac- celerator LU-40 [9] for 2 hours at an electron energy of 40 MeV, the beam pulse length of 1.5 μs, the pulse repetition frequency 50 Hz, and the average current 4.1 μA. The electron beam profile on the converter cor- responded to the Gaussian distribution with the FWHM 1.2 cm. The FWHM of the beam energy spectrum was no more than 2%. Fig. 2 shows the measured profile of the X-Ray flux. After each exposure, the targets were cooled for 24 hours to provide the decay of induced activity caused by short-lived impurities. The isotope activity in the samples was determined with the use of the gamma-spectrometer based on the Canberra HPGe detector with the analyzer InSpector- 2000 and the software Genie 2000. The detector pro- vides the relative registration efficiency of 20 % and the energy resolution of 1.8 keV at a photon energy of 1332 keV (Co-60). The error of specific isotope activity measurement varied within the 7…10% range. The data obtained were normalized to the electron-beam charge value in the course of the target activation. Fig. 2. X-Ray flux distribution behind the converter 2.5. An independent analysis of the target photoacti- vation processes was performed by a simulation method based on the modified transport code PENELOPE-2008 [10]. The yield of photonuclear reactions was calculated by summing their microyields along all the trajectories of all above-threshold photons in the corresponding target device elements [11]. The reaction cross-sections were taken from the database [12]. The processes of target activation by neutrons were not simulated. 3. RESULTS AND DISCUSSION Tables 1 and 2 present the data on the principal iso- tope yield obtained experimentally and by the simula- tion method (in brackets the mass of each target in mg is given). Their analysis shows that the calculated photo- nuclear yield of 101Pd, 184Re in the isotopic targets, and also, of 90Mo and 196Au in the targets-monitors (Table 3) located on the electron beam axis, are in satisfactory agreement with the experimental results. This bears wit- ness to a sufficiently exact description of the reaction cross sections, as well as to adequacy of their computer simulation. The last fact gives grounds for calculation of isotope yields at different modes of target activation. Thus, Figs. 3 to 6 show the yields of 103Pd and 186Re, and also, of the major impurities as function of the elec- tron energy and activation time expressed in terms of half-life of the desired isotope. The yield of 188Re from the Re target 7 without the moderator was determined to be 0.2 μCi/hour⋅μА⋅g. In the presence of the moderator, the yields of 188Re and 198Au in the samples situated on the beam axis and sideways were found to be nearly the same. This con- firms the closeness between the values of neutron fluxes acting on the targets, and permits one to estimate the contribution of neutron-capture channels to the yields of desired isotopes. In the case of palladium, the 102Pd(n, γ) reaction pro- vides no more than 1.5 % of the total yield of 103Pd, this being within the total measurement error. It should be noted that the photonuclear yield of 103Pd was calculated with account of the 104Pd(γ, n)103Pd reaction only. So the experimentally observed excess can be explained by the contribution of the 105Pd(γ, 2n)103Pd channel. In its turn, the 185Re(n, γ) reaction adds ~10 % to the total yield of 186Re. Note that with the use of the moderator, the pro- duction of 188Re increases by more than ten times. Table 1 ISSN 1562-6016. ВАНТ. 2013. №6(88) 198 Isotope yields in Pd targets Isotope Т1/2, days Reaction Yield, µCi/hour⋅µA⋅g Pd-7 (83.5) Pd-10 (84.3) Simulated Experimental Experimental 103Pd 16.9 104Pd(γ, n)103Pd 105Pd(γ, 2n)103Pd 102Pd(n, γ)103Pd 1.8 - - 3.3 0.05 100Pd 3.63 102Pd(γ, 2n)100Pd - 8.6⋅10-2 8⋅10-4 101Pd 0.34 102Pd(γ, n)101Pd 7.6 7.0 0.073 109Pd 0.56 110Pd(γ, n)109Pd 108Pd(n, γ)109Pd 110Pd(γ, p)109Rh→ - - - 62.5 1.6 105Rh 1.47 106Pd(γ, p) 105Rh 105Pd(n, p) 105Rh 108Pd(n, α) 105Ru→ - - - 2.0 0.02 Table 2 Isotope yields in Re targets Isotope Т1/2, days Reaction Yield, µCi/hour⋅µA⋅g Re-7 (852) Re-10 (960) Simulated Experimental Experimental 186Re 3.72 187Re(γ, n)186Re 185Re(n, γ)186Re 49.8 - 56.9 4.6 188Re 0.71 187Re(n, γ)188Re - 3.30 3.25 184Re 38.0 185Re(γ, n)184Re 2.9 2.85 0.6 Table 3 Isotope yields in targets-monitors Target Isotope Т1/2, days Reaction Yield, μCi/hour⋅μА⋅g Simulated Experimental Mo-5 (312) 99Mo 2.75 100Mo(γ, n)99Mo 4.69 5.48 98Mo(n, γ)99Mo - 90Mo 0.24 92Mo(γ, 2n)90Mo 1.56 1.48 Au-7 (111) 196Au 198Au 6.2 2.7 197Au(γ, n)196Au 197Au(n, γ)198Au 5.95 - 5.15 2.65 Au-10 (112) 196Au 198Au 6.2 2.7 197Au(γ, n)196Au 197Au(n, γ)198Au - - 0.62 2.59 0.0 0.2 0.4 0.6 0.8 1.0 0 200 400 600 800 1000 1200 1400 A ct iv ity , µ C i/( µA *g ) t/TPd103 E0 = 30 MeV E0 = 40 MeV E0 = 60 MeV E0 = 80 MeV 1/2 Fig. 3. Specific activity of 103Pd versus time of exposure at different electron energies 0.0 0.2 0.4 0.6 0.8 1.0 0 2000 4000 6000 8000 Ac tiv ity , µ C i/( µA *g ) t / T1/2 Re186 E0 = 30 MeV E0 = 40 MeV E0 = 60 MeV E0 = 80 MeV Fig. 4. Specific activity of 186Re versus time of exposure at different electron energies ISSN 1562-6016. ВАНТ. 2013. №6(88) 199 0.0 0.2 0.4 0.6 0.8 1.0 0 1 2 3 4 A (10 1 P d) /A (10 3 P d) t/TPd103 E0 = 30 MeV E0 = 40 MeV E0 = 60 MeV E0 = 80 MeV 1/2 Fig. 5. Specific activities of 101Pd and 103Pd versus time of exposure 0.0 0.2 0.4 0.6 0.8 1.0 0 100 200 300 400 500 600 A ct iv ity , µ C i/( µA *g ) t/TRe186 E0 = 30 MeV E0 = 40 MeV E0 = 60 MeV E0 = 80 Mev 1/2 Fig. 6. Specific activity of 184Re versus time of exposure at different electron energies CONCLUSIONS A satisfactory fit of experimental results and the simulation data on the photonuclear isotope yield makes it possible to calculate the yields in the thick technolog- ical targets and to compare different methods of isotope production (Tables 4 and 5). For example, from Table 4 it can be concluded that the cyclotron technology has a preference as to the specific and total yields of 103Pd alongside with a low level of impurities. At the same time, it involves a considerable amount of radiochemi- cal procedures, and the produced isotope sources are beyond regeneration. The photonuclear method is capa- ble of providing a high yield of 103Pd in case of using the targets enriched in the 104Pd isotope at much less expenses for the accelerator. In this case, the decayed sources can be reactivated an unlimited number of times. As regards 186 Re (see Table 5), an electron accelera- tor having routine parameters (40 MeV, 250 μA) can provide a considerably higher yield than the reactor and cyclotron technologies do. An additional gain in the yield, along with a reduction in the 184Re yield, can be provided by using the target enriched in 187Re. The cooled sources can also be reactivated. At the same time, the reactor method retains its advantage as to the specific yield of 186Re. Table 4 Comparison between the methods of 103Pd production Facility, parameters Target, reaction, cross-section Yield Major impurities specific total Reactor [1] 4⋅1013 n/сm2⋅s 102Pd, 102Pd(n, γ), 3b 150 μCi/hour⋅g 15 μCi/hour 109Pd, 111Au Cyclotron [2] 20 MeV natRh, 103Rh(p, n), 505 mb (Ep=10 MeV) ~270 μCi/μА⋅hour⋅g 270 μCi/μА⋅hour Carrier-free Electron accelerator [13] 40 МeV natPd, 104Pd(γ, n), 180 mb (Eγ=15 MeV) 4 μCi/μА⋅hour⋅g 50 μCi/ μА⋅hour 100Pd, 101Pd, 109Pd, 105Rh Table 5 Comparison between the methods of 186Re production Facility, parameters Target, reaction, cross-section Yield Major impurities specific total Reactor [1] 3⋅1014 n/cm2⋅s 185Re(>94%), 185Re(n,γ), 112b 7.5 Ci/hour⋅g 75 μCi/hour 188Re Cyclotron [4] 14 MeV natW, 186W(p, n), 80 mb (Ep=9 MeV) ~20 μCi/μА⋅hour⋅g 20 μCi/μА⋅hour Carrier-free Electron accelerator [13] 40 MeV natRe, 187Re(γ, n), 420 mb (Eγ=14 MeV) ~60 μCi/μА⋅hour⋅g ~1 μCi/μА⋅hour 184Re, 188Re REFERENCES 1. Manual for Reactor Produced Radioisotopes // IAEA-TECDOC-1340. 2003. 2. S. Sudar, F. Cserpak, S.M. Qaim. Measurements and Nuclear Model Calculations of Proton-Induced Re- actions on 103Rh up to 40 MeV: Evolution of the Ex- citation Function of the Therapeutic Radionuclide 103Pd // Appl. Rad. Isot. 2002, v. 56, p. 821-831. 3. W.K. Roberts, U.O. Häfeli. Modeling rhenium-186 and rhenium-188 distribution in a neutron-activated rhenium wire and effect of the distribution on beta dosimetry in a water phantom // Appl. Rad. Isot. 1999, v. 51, p. 541-549. 4. E. Persico, M.L. Bonardi, F. Groppi, et al. Excita- tion-functions and yields for Re-186g production by proton cyclotron irradiation // Proc. of 18 Int. Conf. “Cyclotrons and their Applications”. 2007, p. 248-250. ISSN 1562-6016. ВАНТ. 2013. №6(88) 200 5. Making Medical Isotopes:/ Report on the Task Force on Alternatives for Medical Isotopes Produc- tion. TRIUMF, Canada, 2008. www.triump.ca/ repor t-medical-isotope-production. 6. T.V. Malykhina et al. Investigation of the mixed X,n-radiation field at photonuclear production of isotopes // PAST. Series “NPI”. 2008, №5(50), p. 184-188. 7. V.L. Uvarov et al. Two-channel Mode of Mo-99 Pro- duction at an Electron Accelerator // Proc. Conf. IPAC 2011, San Sebastian. Spain. 2011, p. 3627-3629. 8. V.I. Nikiforov et al. A system for measuring the flux profile of high-energy bremsstrahlung // PAST. Se- ries “NPI”. 2008, №3(49), p. 196-200. 9. N.I. Aizatsky, V.I. Beloglazov, V.P. Bozhko, et al. Nuclear-physical complex based on a 100 MeV elec- tron linear accelerator // PAST. Series “NPI”. 2010, № 2(53), p. 18-22. 10. F. Salvat, J.M. Fernández-Varea, J. Sempau. PENELOPE-2008 a Code System for Monte-Carlo Simulation of Electron and Photon Transport // OECD NEA (Issy-les-Moulineaux) France. 2008. 11. V.I. Nikiforov and V.L. Uvarov. Development of the Technique Embedded into a Monte Carlo Transport System for Calculation of Photonuclear Isotope Yield // Nukleonika. 2012, v. 57(1), p. 75-80 (in Russian). 12. Handbook on photonuclear data for Applications // IAEA. TECDOC-1178. 2000. 13. N.I. Aizatsky et al. A powerful electron linear accel- erator with energy up to 40 MeV // PAST. Series “NPI”. 2008, № 3(49), p. 25-29. Article received 23.10.2013 ПОЛУЧЕНИЕ ИЗОТОПОВ Pd И Re В ПОЛЕ СМЕШАННОГО X,n-ИЗЛУЧЕНИЯ УСКОРИТЕЛЯ ЭЛЕКТРОНОВ Н.П. Дикий, В.А. Кушнир, Ю.В. Ляшко, В.В. Митроченко, С.А. Пережогин, Ю.В. Рогов, А.Э. Тенишев, А.В. Торговкин, В.Л. Уваров, В.А. Шевченко, И.Н. Шляхов, Б.И. Шраменко Радиоактивные изотопы палладия (103Pd) и рения (186Re и 188Re) широко используются в ядерной меди- цине. Изучаются условия их получения фотоядерным методом на ускорителе электронов. Исследованы ка- налы наработки целевых изотопов и примесей при облучении мишеней из палладия и рения природного изотопного состава смешанным потоком тормозного излучения с граничной энергией 40 МэВ и фотоней- тронов. Путем размещения конвертера тормозного излучения и мишени внутри модератора нейтронов по- лучены данные по влиянию спектра фотонейтронов на выход изотопов. Методом моделирования изучена также зависимость фотоядерного выхода целевых изотопов и основных примесей от энергии электронов. ОТРИМАННЯ ІЗОТОПІВ Pd І Re В ПОЛІ ЗМІШАНОГО X,n-ВИПРОМІНЮВАННЯ ПРИСКОРЮВАЧА ЕЛЕКТРОНІВ М.П. Дикий, В.А. Кушнір, Ю.В. Ляшко, В.В. Митроченко, С.О. Пережогін, Ю.В. Рогов, А.Е. Тєнишев, О.В. Торговкін, В.Л. Уваров, В.А. Шевченко, І.М. Шляхов, Б.І. Шраменко Радіоактивні ізотопи паладію (103Pd) та ренію (186Re і 188Re) широко використовуються в ядерній медици- ні. Вивчаються умови їх отримання фотоядерним методом на прискорювачі електронів. Досліджено канали напрацювання цільових ізотопів і домішок при опромінюванні мішеней з паладію і ренію природного ізото- пного складу змішаним потоком гальмівного випромінювання з граничною енергією 40 МеВ і фотонейтро- нів. Шляхом розміщення конвертера гальмівного випромінювання і мішені усередині модератора нейтронів отримано дані щодо впливу спектра фотонейтронів на вихід ізотопів. Методом моделювання вивчена також залежність фотоядерного виходу цільових ізотопів і основних домішок від енергії електронів. INTRODUCTION 1. PRINCIPAL REACTIONS 2. EXPERIMENT 3. RESULTS AND DISCUSSION CONCLUSIONS REFERENCES
id nasplib_isofts_kiev_ua-123456789-112093
institution Digital Library of Periodicals of National Academy of Sciences of Ukraine
issn 1562-6016
language English
last_indexed 2025-12-07T17:19:21Z
publishDate 2013
publisher Національний науковий центр «Харківський фізико-технічний інститут» НАН України
record_format dspace
spelling Dikiy, N.P.
Kushnir, V.A.
Lyashko, Yu.V.
Mitrochenko, V.V.
Perezhogin, S.A.
Rogov, Yu.V.
Tenishev, A.Eh.
Torgovkin, A.V.
Uvarov, V.L.
Shevchenko, V.A.
Shlyakhov, I.N.
Shramenko, B.I.
2017-01-17T15:37:46Z
2017-01-17T15:37:46Z
2013
Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator / N.P. Dikiy, V.A. Kushnir, Yu.V. Lyashko, V.V. Mitrochenko, S.A. Perezhogin, Yu.V. Rogov, A.Eh. Tenishev, A.V. Torgovkin, V.L. Uvarov, V.A. Shevchenko, I.N. Shlyakhov, B.I. Shramenko // Вопросы атомной науки и техники. — 2013. — № 6. — С. 196-200. — Бібліогр.: 13 назв. — англ.
1562-6016
PACS: 07.85.-m, 81.40wx,87.53-j,87.53Wz
https://nasplib.isofts.kiev.ua/handle/123456789/112093
Radioactive isotopes of palladium (¹⁰³Pd) and rhenium (¹⁸⁶Re and ¹⁸⁸Re) have found wide use in nuclear medicine. The present report deals with the conditions for their production by a photonuclear method at an electron accelerator. Studies have been made into the channels of target isotope/attendant impurity production as palladium and rhenium targets of natural isotopic composition were exposed to a mixed flux of X-ray (bremsstrahlung) with end-point energy of 40 MeV and photoneutrons. By placing a bremsstrahlung converter and the target inside a neutron moderator, data have been obtained for the effect of photoneutron spectrum on the isotope yield. The simulation technique has been used to investigate the photonuclear yield of target isotopes and major impurities as function of electron energy.
Радіоактивні ізотопи паладію (¹⁰³Pd) та ренію (¹⁸⁶Re і ¹⁸⁸Re) широко використовуються в ядерній медицині. Вивчаються умови їх отримання фотоядерним методом на прискорювачі електронів. Досліджено канали напрацювання цільових ізотопів і домішок при опромінюванні мішеней з паладію і ренію природного ізотопного складу змішаним потоком гальмівного випромінювання з граничною енергією 40 МеВ і фотонейтронів. Шляхом розміщення конвертера гальмівного випромінювання і мішені усередині модератора нейтронів отримано дані щодо впливу спектра фотонейтронів на вихід ізотопів. Методом моделювання вивчена також залежність фотоядерного виходу цільових ізотопів і основних домішок від енергії електронів.
Радиоактивные изотопы палладия (¹⁰³Pd) и рения (¹⁸⁶Re и ¹⁸⁸Re) широко используются в ядерной медицине. Изучаются условия их получения фотоядерным методом на ускорителе электронов. Исследованы каналы наработки целевых изотопов и примесей при облучении мишеней из палладия и рения природного изотопного состава смешанным потоком тормозного излучения с граничной энергией 40 МэВ и фотонейтронов. Путем размещения конвертера тормозного излучения и мишени внутри модератора нейтронов получены данные по влиянию спектра фотонейтронов на выход изотопов. Методом моделирования изучена также зависимость фотоядерного выхода целевых изотопов и основных примесей от энергии электронов.
en
Національний науковий центр «Харківський фізико-технічний інститут» НАН України
Вопросы атомной науки и техники
Применение ускоренных пучков. детекторы и детектирование ядерных излучений
Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator
Article
published earlier
spellingShingle Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator
Dikiy, N.P.
Kushnir, V.A.
Lyashko, Yu.V.
Mitrochenko, V.V.
Perezhogin, S.A.
Rogov, Yu.V.
Tenishev, A.Eh.
Torgovkin, A.V.
Uvarov, V.L.
Shevchenko, V.A.
Shlyakhov, I.N.
Shramenko, B.I.
Применение ускоренных пучков. детекторы и детектирование ядерных излучений
title Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator
title_full Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator
title_fullStr Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator
title_full_unstemmed Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator
title_short Pd and Re isotope production in the field of mixed X,n-radiation of electron accelerator
title_sort pd and re isotope production in the field of mixed x,n-radiation of electron accelerator
topic Применение ускоренных пучков. детекторы и детектирование ядерных излучений
topic_facet Применение ускоренных пучков. детекторы и детектирование ядерных излучений
url https://nasplib.isofts.kiev.ua/handle/123456789/112093
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