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RRFM 2009 Transactions - European Nuclear Society

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177 Lu-octreotate, used for therapy of neuroendocrine tumors, and prepared with imported<br />

177 Lu [3].<br />

188 W is the parent radioisotope of 188 Re, a β - emitter with a half-life of 16.7 hours and is<br />

produced by the reaction 186 W(2n,γ) 188 W. Activation studies complied of the irradiation of W<br />

targets (metallic W and WO 3 ) placed inside an aluminium holder and irradiated for a definite<br />

length of time (2 hours up to 64 hours) with low neutron fluxes (1x10 13 n.cm -2 .s -1 ) and inside a<br />

Be irradiator located at the reactor core with the highest possible flux (4x10 13 n.cm -2 .s -1 ). After<br />

the irradiation, qualitative and quantitative analyses were performed in the targets by γ-<br />

spectroscopy, and 188 Re generators were prepared with the 188 W produced [4,5].<br />

2.5<br />

99 Mo- 99m Tc Gel Generator<br />

99m Tc is the most used radioisotope for diagnosis exams performed in <strong>Nuclear</strong> Medicine<br />

worldwide due to its favorable physical decay properties and its distribution in the generator<br />

form of 99 Mo- 99m Tc [6,7]. In 1996 IPEN started a project aiming the nationalization of the<br />

production of 99 Mo through the 98 Mo(n,γ) 99 Mo reaction and developing the MoZr gel generator<br />

technology [8,9].<br />

Two different targets were tested: metallic Mo and MoO 3 in the form of powder or molten. The<br />

targets were irradiated irradiated for a definite length of time with low neutron fluxes and<br />

inside a Be irradiator located at the reactor core with the highest possible flux. After the<br />

irradiations, the activity of 99 Mo was determined in a dose calibrator and by γ-ray<br />

spectroscopy employing a hiperpure Ge detector from Canberra. 99 Mo was further employed<br />

for the studies aiming the preparation of a MoZr gel type generator.<br />

2.6 Tracer studies<br />

Several tracers were produced in order to help the development of radiopharmaceutical<br />

production methods, such as 122 Sb, 124 Sb, 88 Y and 85 Sr.<br />

Two Sb tracers,<br />

122 Sb and<br />

124 Sb, were prepared to follow the biodistribution of a<br />

pharmaceutical used in the therapy of Leishmanioses, glucantime, and its liposomal<br />

formulations, also to evaluate the amount of Sb incorporated inside the liposomes. The<br />

tracers are produced through the reactions 121 Sb(n,γ) 122 Sb and 123 Sb(n,γ) 124 Sb. Samples of<br />

glucantime and liposomes in clean polypropylene tubes were placed together with antimony<br />

standards inside the aluminium container. Irradiations were carried out at a thermal neutron<br />

flux of 0,8x10 12 n.cm -2 .s -1 for 15 minutes [10].<br />

An important research aiming the nationalization of the production of 90 Y is being carried out<br />

using radioactive tracers produced in the reactor. 90 Y is a radioisotope for use in therapy,<br />

nowadays imported by IPEN at a very high cost and it is produced by a generator system,<br />

90 Sr- 90 Y. The gamma emitting tracers 88 Y and 85 Sr are produced through the reactions<br />

89 Y(n,γ) 88 Y and 84 Sr(n,γ) 85 Sr, respectively, and are employed to optimize the techniques<br />

studied for the development of the generator [11].<br />

The experimental work was developed at the laboratories of the Radiopharmacy Center at<br />

IPEN-CNEN/SP.<br />

3. Results<br />

3.1 Routine production<br />

The local production of 153 Sm meets the total demand for the radiopharmaceuticals<br />

distributed at IPEN. About 74 GBq (2 Ci) of 153 Sm can be produced in one irradiation and the<br />

total activity delivered every week is about 37 GBq (1 Ci).<br />

131 I has a big market in Brazil, and every week more than 1480 GBq (40 Ci) of 131 I<br />

radiopharmaceuticals are distributed by IPEN. Nowadays, with the Reactor operating at 3.5<br />

MW, half of this demand is achieved by the local production (740 GBq – 20 Ci).<br />

249 of 455

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