[en] Palladium-103 (Pd-103) is one of the effective radionuclides for brachytherapy seed. Preliminary study on Palladium-103 production by calculations of Palladium irradiation in G.A. Siwabessy reactor has been carried out. The calculation was performed using natural and enriched Palladium metal with a length of 45 mm and a diameter of 0.8 mm at central irradiation position (neutron flux 1,3xl0¹⁴ n.s^-l.cm^-2) and rabbit system (neutron flux 4xl0¹³ n.s^-1.cm^-2). Calculation results showed that irradiation of natural Palladium at rabbit system for 12 hours resulted in Palladium-103 with radioactivity of 4.27 MBq at the end of irradiation (EOI), lower than the minimum radioactivity for seed (37 MBq). Irradiation of enriched Palladium (Pd-102 enrichment 89%) at rabbit system resulted in Pd-103 with radioactivity of 387 MBq at EOI. Radionuclide impurities of Pd-109 and Pd-111 were produced in the irradiation process. Radioactivity of Pd-111 decreased rapidly since the half life is very short (23.3 min). Radionuclide impurity of Pd-109 decreased to less that 0.1% of Pd-103 radioactivity after 6.3 days. The radioactivity of Pd-103 became 299 MBq 6.3 days after irradiation. Irradiation of natural Palladium at central irradiation position resulted in Pd-103 with radioactivity of 265 MBq at EOI. Radioactivity of Pd-109 was 4390 MBq at EOI and decreased to less than 0.1% of Pd-103 radioactivity after 8,3 days. The radioactivity of Pd-103 decreased to 189 MBq after the decay time. (author)

[en] Preparation of ⁹⁹Mo/^99mTc radioisotope generator using irradiated natural molybdenum requires a sorbent with high sorption capacity. Zirconium-based materials (ZBM), sorbent with sorption capacity of about 183 mg Mo/g ZBM, has been successfully synthesized. However, the sorbent was easily broken in the Mo sorption process due to many fractures in the grain. To increase the hardness, the material was immersed in tetraethyl orthosilicate (TEOS), drained and then heated. The hardness test results showed that the ZBM with TEOS treatment was not broken when immersed into the Mo solution. Observations using SEM showed that the fractures formed on the ZBM were successfully removed by TEOS treatment. Measurements using EDS showed that after TEOS treatment, the silicon was detected and the oxygen content increased in the material surface. Sorption test results showed that the TEOS treatment decreased the sorption capacity of molybdenum from 183 to 79.8 mg of Mo per gram of sorbent. It is necessary to examine further the material in preparation of ⁹⁹Mo/^99mTc radioisotope generator using irradiated natural Mo to obtain the characteristics of the generator using the ZBM adsorbent. (author)

[en] Center for Radioisotope and Radiopharmaceutical has been successful in iodine-125 production tests using enriched xenon gas. However, the radionuclide impurity of iodine-125 was detected in the 7^th production test. The radioactivity of iodine-126 in irradiation chamber could not be measured directly. The calculation of iodine-126 radioactivity at irradiation chamber, therefore, has been carried out. In this calculation, xenon-124 with enrichment of 82.4% was irradiated for 24 hours with neutron flux of 3x10¹³ n.s^-1.cm^-2. Calculation results showed that irradiation for 24 hours resulted in 11.7 mCi of iodine-126. After moving the xenon gas to the decay pot, the iodine-125 remained in the irradiation chamber. The iodine-125 was irradiated during reactor operation. At the end of 12^th day, the radioactivity of iodine-126 was 367 mCi. It revealed that most of the iodine-125 in the 7^th test product was iodine-125 produced in the previous production test. The mass of iodine in irradiation chamber when the xenon gas moved from irradiation chamber was 0.33 mg. This value was useful as a reference in the iodine filter maintenance. (author)

[en] Production tests of Iodine-125 have been carried out using enriched xenon target with 82,4% of ¹²⁴Xe enrichment. The target was irradiated at irradiation chamber in S1 position of G.A. Siwabessy reactor. After irradiation for 24 hours, the irradiated xenon gas was decayed at decay pot for 7 days. The produced iodine-125 was dissolved 3 times using NaOH 0.005N. From 1^st to 8^th tests, the total radioactivities were 9541, 9801, 11239, 9458, 3293. 3735, 4693 and 2744 mCi. The decrease of the total radioactivity was caused by the decrease of the gas target. Radioactivity of the 1^st solution depended on the volume of NaOH solution. The average percentages of the 1^st solution were 65.1, 71.5 and 82.6% of the total radioactivity for 3, 4 and 5 mL of NaOH. The maximum radioactivity concentration was 3410 mCi/mL from 1^st solution of the 1^st production test. (author)

[en] Iridium-In is one of the radioisotopes used in gamma radiography. Calculation for producing iridium-In using G.A. Siwabessy nuclear reactor has been carried out. The targets were discs with 2.7 mm in diameter and 0.15 mm in thickness. The neutron flux was the value at the central irradiation position as high as 1.3 x 10"1"4 n.s"-"1.cm"-"2. Calculation results showed that iridium metal irradiation for 12 days resulted in iridium-192 with radioactivity of 96.8 GBq per disc at the end of irradiation. If the irradiation was continued to the next irradiation period after 16 days of shut down, the irradiation resulted in 171.2 GBq of iridium-In. If the target was irradiated continuously for 40 days, the irradiation resulted in 284.5 GBq of iridium-192. The resulted radionuclide impurity was iridium-194 which decayed rapidly with half life of 19.15 hours. The initial radioactivity required for effective radiation source for gamma radiography was 3700 GBq in a radiation source. If the target was irradiated with shut down, the discs required in a radiation sources were 24 discs. If the target was irradiated continuously, the required discs were 14 discs in a radiation source. (author)

[en] Radioisotope, radiopharmaceutical and cyclotron technologies are extensively developed, increasing the contribution to solve the problem of community. Radioisotopes can be produced by neutron irradiation in a nuclear reactor or by irradiation of charged particles using a cyclotron. Along with the development of radioisotope technology, new radioisotopes or new radioisotope production methods have been successfully developed. Cyclotron utilization technology continues to evolve by utilizing high energy charged particles. Several radioisotope and radiopharmaceutical production technologies, as well as the utilization of cyclotron have been successfully developed in Indonesia. Research and development results in the form of diagnostic agents, therapeutic agents, radioassay technologies and radioactive tracers have been successfully obtained. In the development of diagnostic agents, several diagnostic radioisotope and radiopharmaceutical production technologies have been successfully developed. Some of the production technologies have been utilized by pharmaceutical industry to meet the needs of community. In therapeutic agent, production technologies of therapeutic radioisotope, therapeutic radiopharmaceutical and sealed source have been developed. In radioassay technology development, production technologies of radioimmunoassay (RIA) / immunoradiometric assay (IRMA) kits and the utilization of radioligand binding assay (RBA) have been successfully developed. In the radioactive tracers, production technologies of tracers for industry, biomedical research, natural resources and the environment management have been successfully obtained. The next challenge is the utilization of the technologies, so that the technologies are more beneficial to the community. In the utilization of the technologies, intensive cooperation among research and development institutions, industries, users and regulatory bodies are required. (author)

[en] Clean room for aseptic production process of radiopharmaceutical kit requires controlled facilities of good environmental condition, particularly the amount of particle and microbiological contamination. In the book of Good Manufacturing Practice (CPOB) the condition of the maximum limitation of particle and microbiological contamination when in non operation and operational has been listed. Therefore, it is necessary to conduct research related to the monitoring of particle and microbiological contamination in the clean room environment. Monitoring of particles and microbiological contamination was conducted at several points in A, B, and C class for 4 batches of production during non operation and operational. Monitoring of microbiological contamination was conducted using Microbial Air Sampler during non operation and (settle plate; contact plate) during operational. The results of monitoring of particle contamination for particle size of 0.5 μm and 5 μm during non operation were A class (19.3 and 0.1), B (92.9 and 0.7), and C (89.9 and 11.4) while operational monitoring of particle size 0.5 μm and 5 μm in A class were 830.5 and 1.5. The average of microbiological monitoring on non operation in A, B, and C class were 0.4; 0.1; 2.4. The average of microbiological monitoring on operational in A, B, and C class were 0.1; 1.4; 2.5 for settle plate and 0.1; 0.0; 0.2 for contact plate. All the particle and microbiological monitoring data obtained showed values below the required maximum. Therefore, it can be concluded that clean room is still feasible to be used for radiopharmaceutical kit production. (author)

[en] Preparation of ⁹⁹Mo/^99mTc radioisotope generator using irradiated natural molybdenum requires an adsorbent with high absorption capacity. Zirconium-based materials (ZBM), adsorbent with adsorption capacity of about 183 mg(Mo) / g(adsorbent), has been successfully synthesized. However, the adsorbent was easily broken in the Mo adsorption process due to many fractures in the grain. To increase the hardness, the material was immersed in tetraethyl orthosilicate (TEOS) and coated by TEOS flow in a column. The hardness test results showed that the ZBM with TEOS treatment was not broken when immersed into the Mo solution. Observations using SEM showed that the fractures formed on the ZBM were successfully removed by TEOS treatment. Measurements using EDS showed that after TEOS treatment, the silicon was detected and the oxygen content increased in the material surface. Adsorption test results showed that the TEOS immersion decreased the adsorption capacity of molybdenum from 183 to 79.8 mg of Mo per gram of adsorbent. The TEOS flow-in a column gave material with relatively high adsorption capacity, 140 mgMo per gram adsorbent. The content of Silicon in the surface was lower than that of adsorbent immersed in TEOS. (author)

[en] Development of polymers application is more advanced, nowadays. Poly-N-isopropiiacrilamide (PNIPA) is a hydrogel polymer used in a wide range of both industrial and medical fields. PNIPA/PVP IPNs labelled with I-125 has a potential usage for cancer therapy source matrix. The purpose of this research is to obtain synthesis protocol of the PNIPA/PVP IPNs labelled with I-125 and its characterization. Prior, PNIPA/PVP IPNs was synthesized using ammonium peroxide as redox initiator and tetraetilendiamin. Then, various concentration of polivinilpirolidone (PVP) was added into the PNIPA polymer solution, i.e 0.5 %; 1% and 1.5 % w/w. To obtain a optimal PNIPA/PVP polymer which was labelled with sodium iodide (Na¹²⁵I). PNIPA/PVP IPNs were analysed by H-NMR and FTIR. PNIPA/PVP IPNs has been successfully synthesized with PVP concentration of 0.5 % with transition temperature and viscosity of 34-36 °C and 14.46 mm²/s respectively and the yield of PNIPA/PVP labelled with I-125 is 90 %. H-NMR analysis result just showed the chemicals shift from PNIPA polymer and FTIR result of PNIPA/PVP IPNs polymer showed infra red absorption from functional groups of Panpipe polymer. PNIPA/PVP IPNs Polymer has been successfully synthesized, but its stability has to be observed as well as the radiochemical purity of PNIPA/PVP IPNs polymer labelled with I-125. (author)

[en] The Proceeding of Annual Scientific Meeting of Radioisotopes, Radiopharmaceutical, Cyclotron and Nuclear Medicine held in Semarang on 10 - 11 October 2014. This scientific meeting theme is Current Advances in Radionuclide Technology, Nuclear Medicine and Molecular Imaging by involving researchers from the Radioisotope and Radiopharmaceutical Technology Center – BATAN) and universities, nuclear medicine practitioners and visiting speakers from abroad. The proceeding consist of 14 articles from BATAN participant and others. (MPN)