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1.
Excitation functions were measured for (p, 2n) and (p, pn) reactions on 99.9% enriched 124Xe from threshold up to 44 MeV. The (p, 2n) reaction is much stronger than the (p, pn) channel; above 36 MeV, however, the two processes have almost equal cross sections. Differential yields of 123I were measured experimentally as a function of proton energy and were also calculated from the excitation functions. Our experimental and theoretical yield data are consistent within 15%, but are lower by a factor of 2 than the literature experimental values. Our studies show that the optimum energy range for the production of 123I is Ep = 29 → 23 MeV. The theoretically expected thick target yield of 123I at 6.6 h after EOB is 11.2 mCi/μAh, and is in agreement with the high-current experimental production yields.  相似文献   

2.
The 118Te/118Sb generator has potential application for positron emission tomography. In this study, we modelled the production of the 118Te precursor via proton activation of 122Te and 123Te targets. 118Te excitation functions were calculated for the (p, xn) and (p, pxn) production channels using a compound nucleus/statistical evaporation approach. These calculations indicate that 118Te can be produced in GBq (100 mCi) quantities by the irradiation of a thin (0.4 g/cm2) enriched 122Te target with 62 MeV protons. This corresponds to a cumulative 118Te production rate in the 62-60 MeV proton energy region of 16 GBq/C (1.6 mCi/μA-h). In this proton energy range, 118Te production is maximized while the production of such contaminant nuclides as 119Te is relatively low. In view of the sizable 118Te production rate estimate, we are proceeding with the development of optimal Te/Sb separation chemistry applicable to a generator system.  相似文献   

3.
The excitation function of the 122Te(d, n)123I nuclear reaction has been measured from threshold up to 21 MeV by the stacked foil irradiation technique. Good agreement was obtained with the results of the recent model calculations but an energy shift of 2 MeV to lower energy can be seen when comparing with cross section measured earlier. Integral yields have been deduced from the measured excitation function and have been compared with experimental thick target yields found in the literature. A comparison of the yields of the proton and deuteron induced reactions for production of 123I is given.  相似文献   

4.
Cross-section data for the production of medically important radionuclide 124I via five proton and deuteron induced reactions on enriched tellurium isotopes were evaluated. The nuclear model codes, STAPRE, EMPIRE and TALYS, were used for consistency checks of the experimental data. Recommended excitation functions were derived using a well-defined statistical procedure. Therefrom integral yields were calculated. The various production routes of 124I were compared. Presently the 124Te(p,n)124I reaction is the method of choice; however, the 125Te(p,2n)124I reaction also appears to have great potential.  相似文献   

5.
A simple method is described for the production of high quality clinical 123I hippuran at TRIUMF. The first feature is that solid ortho-iodo-hippuric acid (IHA) is heated with aqueous [123I]iodide creating a single phase where labelling occurs. When subsequently cooled to room temperature, IHA crystallizes. The second feature is employed at this stage. A density gradient is created with NaCl to remove the supernatant fluid from the IHA crystals. The IHA is then neutralized for pharmaceutical use. The product purity is consistantly >99% by TLC and by HPLC analysis that is described. The initial tag is typically 96% and the useful recovery is 85% by this process. Iodine-123 has been used up to 100 mCi per batch from the 500 MeV 133Cs (p, 2p, 9n) 123Xe reaction and from the 124Xe (p, 2n) 123Xe reaction.  相似文献   

6.
Excitation functions of the nuclear reactions 124Te(d,xn)124-125I were measured from their respective thresholds up to 14.0 MeV via the stacked-foil technique. Thin samples were prepared by electrolytic deposition of 99.8% enriched 124Te on Ti-backing. The excitation function of the 124Te(d,n)125I reaction was measured for the first time. The present data for the 124Te(d,2n)124I reaction are by an order of magnitude higher than the literature experimental data but are in good agreement with the results of a hybrid model calculation. From the measured cross sections, integral yields of 124,125I were calculated. The energy range Ed = 14 --> 10 MeV appears to be the best compromise between 124I-yield and 1251-impurity. The calculated 124I-yield amounts to 17.5 MBq/microA h and the 125I-impurity to 1.7%. A critical evaluation of the three nuclear routes for the production of 124I, viz. 124Te(d,2n)-, 124Te(p,n)- and 125Te(p,2n)-processes, is given. The reaction studied in this work proved to be least suitable. The 124Te(p,n)-reaction gives 124I of the highest radionuclidic purity, and a small-sized cyclotron is adequate for production purposes. The 125Te(p,2n)-reaction is more suitable at a medium-sized cyclotron: the yield of 124I is four times higher than in the other two reactions but the level of 0.9% 125I-impurity is relatively high.  相似文献   

7.
Excitation functions of the nuclear reactions 125Te(p, xn) (119,120m, 120g, 121,122,123,124,125)I were measured for the first time from their respective thresholds up to 100 MeV using the stacked-foil technique. Thin samples were prepared by electrolytic deposition of 98.3% enriched 125Te on Ti-backing. In addition to experimental studies, excitation functions were calculated by the modified hybrid model code ALICE-IPPE. The experimental and theoretical data generally showed good agreement. From the measured cross section data, integral yields of (123,124,125)I were calculated. The energy range Ep 21 --> 15 MeV appears to be very suitable for the production of the medically interesting radionuclide 124I (T(1/2) = 4.18 d; I(beta)+ = 25%). The thick target yield of 124I amounts to 81 MBq/microA h and the level of 125I-impurity to 0.9%. The 125Te(p,2n)124I reaction gives 124I yield about four times higher than the commonly used 124Te(p,n)124I and 124Te(d,2n)124I reactions. The proposed production energy range is too high for small cyclotrons but large quantities of 124I can be produced with medium-sized commercial machines.  相似文献   

8.
Following the decay of a sample of 123I, it was found after about two weeks the decay no longer corresponds to a half life of 13.21 h, but to a longer half life equal to that of 123mTe.After a chemical separation of iodine/tellurium, and comparing the measured activities with a reference solution, the branching ratio of 123I/123mTe was found to be (7.7 ± 0.2) 10−5.  相似文献   

9.
The production of high-purity (123)I that utilizes an isotopically enriched (124)Xe target and bombardment with 30MeV protons, through the reactions (124)Xe (p, 2n) (123)Cs-->(123)Xe-->(123)I and (124)Xe (p, pn) (123)Xe-->(123)I, is described. The aim of this work was to improve the production parameters, such as (124)Xe load pressure, beam current, decay time and target heating to recover (123)I to obtain high-production (123)I yield at low cost.  相似文献   

10.
(124)I was produced, via (124)Te(p,n)(124)I reaction, in greater than 3.7GBq (100 mCi, EOB) amount by bombarding (124)TeO(2) targets at 24 microA current for about 8h. This was achieved by keeping the target at 37 degrees relative to the beam during irradiation, by sweeping the beam across the target and by keeping the incident energy of the proton at 14.1MeV. The time-averaged yield of our 8h run was 21.1 MBq/microAh (0.57 mCi/microAh), which was 90% of the theoretical yield calculated using thick target yield data obtained from the reported excitation function for the reaction. At the end of bombardment, the level of (125)I and (126)I impurities, co-produced with (124)I, were 0.03% and 0.007%, respectively.  相似文献   

11.
The binary compound, aluminum telluride (Al(2)Te(3)), was investigated as a target material for the production of (124)I by way of the (124)Te(p,n)(124)I reaction on a low-energy cyclotron. The high melting point and formation of a glassy matrix upon heating provided a stable target material at irradiations up to 20 microA of 11 MeV protons. The 87% tellurium mass fraction and 95% iodine separation yield led to significantly higher quantities of iodine compared to traditional TeO(2)/6%Al(2)O(3) admixtures. Radiochemical analysis of distilled samples using ion chromatography showed that the product remained in the iodide form while supported in weak buffer solutions. Stable Te impurities in the radioiodine product were less than 0.5 microg following purification by ion exchange chromatography. Average thick target yields of 229+/-18 microCi/microAh were achieved, and typical production runs at 18 microA for three hours yielded 12 mCi at the end-of-bombardment. Total losses of the target material after each irradiation and distillation cycle were approximately 2%.  相似文献   

12.
Using the technology described for electrodeposition of elemental tellurium, it is possible to bombard a target with 2 kW of proton beam power without significant loss of radio iodine. If Te-123 enriched to 96% is used as target material, the I-123 yield would be about 1 Curie with a 0.23% I-124 impurity for a 2-h bomardment with 130 muA of 15 MeV protons. The same I-124 impurity level can be maintained with a lower enrichment of Te-123 by reducing the proton energy to 11.5 meV, but with a consequent reduction in I-123 yield.  相似文献   

13.
Using the technology described for electrodeposition of elemental tellurium, it is possible to bombard a target with 2 kW of proton beam power without significant loss of radio iodine. If Te-123 enriched to 96% is used as target material, the I-123 yield would be about 1 Curie with a 0.23% I-124 impurity for a 2-h bombardment with 130 A of 15 MeV protons. The same I-124 impurity level can be maintained with a lower enrichment of Te-123 by reducing the proton energy to 11.5 meV, but with a consequent reduction in I-123 yield..  相似文献   

14.
Excitation functions of the nuclear reactions 120Te(d,xn)121,120m,gI were measured for the first time from their respective thresholds up to 13.5 MeV. Thin samples prepared by electrolytic deposition of 99.0% enriched 120Te on Ti-backing were used. Integral yields of 121,120m,gI were calculated from the measured cross section data. A comparison of the 122Te(p,3n)-, 120Te(p,n)- and 120Te(d,2n)-processes for the production of 120gI is given. The 120Te(d,2n)-process is unsuitable for production purposes since the yield of 120gI is very low and the level of 121I impurity very high. The choice lies either on the 122Te(p,3n)- or the 120Te(p,n)-reaction and is governed by the available proton energy and the financial resources for procuring the enriched target material.  相似文献   

15.
Purpose The non-pure positron-emitting iodine isotope 120I (T 1/2=81 min) is a short-lived alternative to 124I. 120I has a positron abundance more than twice that of 124I and a maximum positron energy of 4 MeV. This study was undertaken to evaluate and characterise the qualitative and quantitative PET imaging of 120I.Methods 120I was produced via the 120Te(p,n) reaction on highly enriched 120Te. The measurements were done with the Siemens scanner HR+ and the 2D PET scanner GE PC4096+. A cylinder containing three cold inserts and a phantom resembling a human brain slice were used to evaluate half-life, positron abundance and background correction. To analyse the image resolution, a 1-mm tube placed in water was filled with 120I and 18F. Comparisons with 18F, 124I and 123I (measured with SPECT) were made using the Hoffman 3D brain phantom.Results The half-life of 81.1 min was reproduced by the PET measurements. The PET-based positron abundance ranged from 47.9% to 55.0%. The reconstructed image resolution found with the HR+ was 5.4 mm FWHM (12.3 mm FWTM), in contrast to 4.6 mm (8.6 mm) when using 18F. Erroneous positive and negative numbers of radioactivity found in the cold inserts became nearly zero when the background of γ-coincidences was corrected for. Images of the Hoffman phantom were inferior to those obtained when 18F or 124I was applied but superior to the 123I-SPECT images.Conclusion Our data show that 120I of high radionuclidic purity can be regarded as a suitable nuclide for the PET imaging of radioiodine-labelled pharmaceuticals.  相似文献   

16.
In order to optimize the production of 118Te in thick targets for use in a 118Te/118Sb radionuclide generator, the excitation function for the 121Sb(p,4n)118Te reaction has been measured for 30–46 MeV protons. The excitation functions for the competing reactions natSb(p,xn)119mTe, natSb(p,xn)119Te, natSb(p,xn)121mTe, natSb(p,pxn)120mSb and 123Sb(p,pn)122Sb have also been determined using stacked foil techniques. The 121Sb(p,4n)118Te reaction cross section maximum was found to be 480 mbarn at 44 MeV. In order to minimize the 119m + 119Te interference a minimum proton beam energy of 40 MeV is required. The cross section results are compared with published data and with calculated excitation functions.  相似文献   

17.
Excitation functions of the nuclear reactions 120Te(p,xn)119,120m,gI were measured for the first time from their respective thresholds up to 35 MeV. Use was made of the stacked-foil technique. Thin samples were prepared by electrolytic deposition of highly enriched 120Te (99.0%) on Ti-backing. Integralyields of 119,120m,gI were calculated from the measured cross section data. For the production of the medically interesting β+-emitting radioisotope 120gI (T1/2=1.35 h) the energy range Ep=16→9 MeV appears to be optimum, the thick target yield of 120gI amounting to 2.3 GBq (62 mCi)/μAh and the 120mI and 119I impurity levels to 4.8 and 4.4%, respectively. A comparison of the 122Te(p,3n)- and 120Te(p,n)-processes for the production of 120gI is given. Despite the higher cost of the target material, the 120Te(p,n)-process is superior since a small-sized cyclotron is adequate and the radionuclidic quality of the product is better.  相似文献   

18.
Optimisation experiments on the production of the positron emitting radionuclides 124I(T(1/2) = 4.18d) and (120g)I (T(1/2) = 1.35 h) were carried out. The TeO(2)-target technology and dry distillation method of radioiodine separation were used. The removal of radioiodine was studied as a function of time and the loss of TeO(2) from the target as a function of oven temperature and time of distillation. A distillation time of 15 min at 750 degrees C was found to be ideal. Using a very pure source and comparing the intensities of the annihilation and X-ray radiation, a value of 22.0 +/- 0.5% for the beta(+) branching in 124I was obtained. Production of 124I was done using 200 mg/cm(2) targets of 99.8% enriched 124TeO(2) on Pt-backing, 16 MeV proton beam intensities of 10 microA, and irradiation times of about 8 h. The average yield of 124I at EOB was 470 MBq(12.7 mCi). At the time of application (about 70 h after EOB) the radionuclidic impurity 123I (T(1/2) = 13.2 h) was <1%. The levels of other impurities were negligible (126I < 0.0001%;125I = 0.01%). Special care was taken to determine the 125I impurity. For the production of (120g)I only a thin 30 mg target (on 0.5 cm(2) area) of 99.9% enriched 120TeO(2) was available. Irradiations were done with 16 MeV protons for 80 min at beam currents of 7 microA. The 120gI yield achieved at EOB was 700 MBq(19 mCi), and the only impurity detected was the isomeric state 120 mI(T(1/2) = 53 min) at a level of 4.0%. The radiochemical purity of both 124I and 120gI was checked via HPLC and TLC. The radioiodine collected in 0.02 M NaOH solution existed >98% as iodide. The amount of inactive Te found in radioiodine was <1 microg. High purity 124I and 120gI can thus be advantageously produced on a medium scale using the low-energy (p,n) reaction at a small-sized cyclotron.  相似文献   

19.
The existing cross section data of the natEu(d,x) and natEu(p,x) reactions relevant for the production of 147,149Gd were expanded up to 70.9 MeV and 44.8 MeV, respectively. Integral yields of radiogadolinium were calculated, showing production rates higher than for the earlier proposed irradiation of highly enriched 144Sm with α- or 3He-particles. The formation of radioisotopic impurities like 151Gd (T1/2=124 d) and 153Gd (T1/2=240 d) was below 5%. Production of 147,149Gd using enriched europium is also discussed.  相似文献   

20.
Excitation functions of the reactions (nat)Sb((3)He,xn)(124,123,121)I were measured from their respective thresholds up to 35 MeV, with particular emphasis on data for the production of the medically important radionuclide (124)I. The conventional stacked-foil technique was used. From the experimental data the theoretical yields of the three investigated radionuclides were calculated. The yield of (124)I over the energy range E9(30He) = 35 --> 13 MeV amounts to 0.95 MBq/microA h. The radionuclidic impurities are discussed. A comparison of (3)He- and alpha-particle-induced reactions on antimony for production of (124)I is given. The alpha-particle-induced reaction on enriched (121)Sb and the (3)He-particle-induced reaction on enriched (123)Sb would lead to comparable (124)I yields, but the level of impurities in the latter case would be somewhat higher.  相似文献   

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