[en] Short communication. 6 refs

No abstract available

[en] The neutron spectrum in the cyclotron cavern located at the Nuclear Engineering Institute (IEN), Brazil, was measured for the reaction Te¹²⁴ (p,n) I¹²³. The measurements were made in three different points using manganese, copper, indium, iron, nickel and gold foils. The neutron spectrum found is essentially thermal and intermediate and also includes a fast component. The measurements were performed for radioprotection purposes. (author). 7 refs., 7 figs., 6 tabs

[en] Iodine-124 (T_1/2 = 4.18 d) is an important radionuclide for preclinical research in positron emission tomography (PET). We describe an improved method to produce and extract ¹²⁴I from a solid [¹²⁴Te]TeO₂ target efficiently using the dry distillation technique. Our process is based on remote hot cell handling and was optimised to achieve efficiencies better than 90% with an average thick target yield of 9.0 ± 1.0 MBq/μAh (n = 47, corrected for decay). The technology is safe and reduces the dose to the operator. (orig.)

No abstract available

No abstract available

[en] The isotope iodine 123 is obtained via the reaction 124 Te (p,2n)I 123 where the proton flow has an energy of 26 MeV. The target is enriched to 96% with Te 124. The target carrier is water cooled. The extraction of the iodine 123 is done by dry distillation at temperatures >= 730⁰C. The yield is 9 mci/μA/h. The target is present as tellurium dioxide glass target. (DG)

[en] These studies had the purpose of establishing the optimal conditions for the production of ¹²³I through the ¹²⁴Te (p,2n) ¹²³I reaction, using the CV-28 Cyclotron (E_max = 24 MeV for protons) at IPEN-CNEN/SP. Two different targets (TeO₂ and TeO₂ + 2% Al₂O₃) were irradiated in order to check their physical resistance against beam current (up to 12 μA) and length of irradiation (10 min - 2 h), and to evaluate the recovery of the radioiodine produced, by a dry distillation process with a high frequency induction furnace. Later on, enriched ¹²⁴TeO₂ (96.2%) targets were irradiated and ¹²³I was produced routinely with a production yield of (3.31 ± 0.07) mCi/μAh, 1.7% of ¹²⁴I at EOB and radiochemically pure. (author) 8 refs.; 1 fig.; 1 tab

[en] A relatively simple and therefore inexpensive method of producing the isotope ¹²³I, which plays an important role in nuclear medicine, via the reaction ¹²⁴Te(p,sup(2n))¹²³I is presented. (WL)

[en] Short communication