[en] The paper summarizes the preparation and quality control of ¹⁵³Sm-EDTMP and three ¹⁵³Sm-radiosynovectomy agents. Natural and enriched Sm₂O₃ (98.7% ¹⁵²Sm) irradiated in RSG-GAS 30 MW reactor yielded pure and high specific activity ¹⁵³Sm. Labeling of EDTMP with ¹⁵³Sm was carried out by mixing ¹⁵³SmCl₃ solution of pH 4.0 to an EDTMP solution at room temperature then pH adjustment to 8. The ¹⁵³Sm-EDTMP complex was separated from the free ¹⁵³Sm⁺³ on a Chelex 100 column. Radiochemical purity was determined by thin layer chromatography using Cellulose sheets and pyridine: ethanol: water (1: 2: 4) mixture as solvent. The ¹⁵³Sm-EDTMP has been shown to be stable for two weeks. Three particulate preparations of ¹⁵³Sm used for the irradiation of chronic synovitis have been studied. They are hydroxyapatite particles, human serum albumin microspheres and ferric hydroxide macroaggregates. The ¹⁵³Sm-ferric hydroxide macroaggregates were prepared in a single step by coprecipitation of ¹⁵³Sm in the formation of Fe(OH)₃. Preparation of ¹⁵³Sm-labelled hydroxyapatite particles and ¹⁵³Sm-labelled albumin microspheres were carried out by ¹⁵³Sm labelling of previously prepared particles. Radiolabelling efficiency were greater than 95% for hydroxyapatite particles and macroaggregates and was lower than 20% for albumin microspheres. The particle sizes were inspected using an optical microscope with a haemocytometer and micrometric ocular. (author)

[en] The irradiation, disassembly, and processing of two full-scale low-enriched uranium (LEU) targets were recently demonstrated by personnel in the BATAN PUSPIPTEK Facilities (Serpong, Indonesia). Targets were fabricated at Argonne National Laboratory (Argonne, IL, U.S.A.) and shipped to PUSPIPTEK. The processing was done by nearly the same procedure used for the production of ⁹⁹ Mo from high-enriched uranium (HEU) targets. The BATAN Radioisotope Production Centre produces ⁹⁹ Mo using the cintichem process by first dissolving the uranium in an acid cocktail; three proprietary separation steps recover the ⁹⁹ Mo and purify it from other components of the irradiated uranium. Processing of LEU-metal targets is nearly identical to that used for HEU-oxide targets except (1) a separate dissolver is required and (2) the dissolution cocktail is nitric acid alone rather than a nitric/sulfuric acid mixture. The demonstrations went smoothly except for problems with sampling and gamma analysis to assess product purity. foils could be removed from targets fabricated from zirconium and/or 304 stainless steel, and processing produced an equivalent yield of ⁹⁹ Mo/²³⁵ U to that of the HEU target. (author)

[en] Production process of 99Mo from fission of 235U in RPC- BATAN produces non-moly radioactive fractions, which are classifiable into 3 fraction, i.e.; radioiodine fraction, radioxenon (noble gas) fraction and post-irradiated uranium fraction. The radioiodine fraction is expectable to be used as a source for providing radioisotope of 131I, and, therefore, an effort for separation of the radioiodine fraction was carried out. The separation was performed by trapping the radioiodine in a copper-wool column followed by purification using charcoal column. The bulk solution of Na131I bulk solution was relatively low, presumable due to the escape of the radioiodine from the copper-wool column into the cold finger originally used for trapping the noble gas fraction

[en] The high performance adsorbent Poly Zirconium Compound (PZC) was produced by Department of Radioisotope, Japan Atomic Energy Research Institute. This compound was developed as an adsorbent for natural Mo (n,γ) ⁹⁹Mo-^99mTc Generator. In the present paper, we report the performance of the PZC for a ^99mTc Generator which was focused on the yield, on elution profile and ⁹⁹Mo breakthrough. (author)

[en] In March and September 1999, demonstrations of the irradiation, disassembly, and processing of LEU metal foil targets were performed in the Indonesian BATAN PUSPIPTEK Facilities. These demonstrations showed that (1) irradiation and disassembly can be performed so that the uranium foil can be easily removed from the target body, and (2) with only minor changes to the current process, the LEU foil can produce yield and purity of the ⁹⁹Mo product at least as great as that obtained with the HEU target. Further, because of these modifications, two hours are cut from the processing time, and the liquid waste volume is reduced. Results of these demonstrations will be presented along with conclusions and plans for future work

No abstract available

[en] In March and September 1999, demonstrations of the irradiation, disassembly, and processing of LEU metal foil targets were performed in the Indonesian BATAN PUSPIPTEK Facilities. These demonstrations showed that (1) irradiation and disassembly can be performed so that the uranium foil can be easily removed from the target body, and (2) with only minor changes to the current process, the LEU foil can produce yield and purity of the ⁹⁹Mo product at least as great as that obtained with the HEU target. Further, because of these modifications, two hours are cut from the processing time, and the liquid waste volume is reduced. Results of these demonstrations will be presented along with conclusions and plans for future work. (author)