[en] Toluidine blue labelled with radioiodine has been used for cholescintigraphy. The labelling of toluidine blue with radioiodine (¹³¹I) by means of reaction at room temperature is presented here. The use of iodide-iodate system in an acidic solvent (0.1 N HCl) gives more labelling yield than H₀₂ or iodomonochloride method. It was presumed that the labelling mechanism is an electrophilic substitution which gives two isomers, but the mole ratio of iodide-iodate does not meet the reaction stoichiometrics. Both the starting material and the resulting iodinated compound gave the same absorption in the visible region while chromatographic determination did not separate them. The separation of inorganic iodide was carried out with Dowex 1x8 (Cl^-) 50-100 mesh anion exchange resin in a 3 ml disposable syringe barrel falled to the 1 ml mark. The radiochemical purity was determined by paper chromatography followed by counting and autoradiography. The use of n-butanol-acetic acid-water mixture (60:15:25, v/v) and 28% NH₄OH-water mixture (1:4, v/v) as the eluting solvent gave not more than 2% difference in the result, but the later had some advantages. The yield of 20-24 hours reaction ranged between 80-90% with less than 2.5% of radiochemical impurity. It was observed that inorganic iodide was released during storage, but after 10 days of ordinary storage conditions the radiochemical impurity was not more than 5%. (author)

[en] The ¹⁴C-methyl labelled tryphenylmethylphosphoniumiodide had been synthesized using Ba¹⁴CO₃ as the starting material. The synthesis of this labelled compound covered 4 steps, i.e.: liberation of ¹⁴CO₂ from Ba¹⁴CO₃ followed by reduction of the ¹⁴CO₂ to produce ¹⁴CH₃OH which was than reacted with HI and finally the resulting ¹⁴CH₃I was reacted with triphenylphosphine. Using 5 mmole of Ba¹⁴CO₃ (89,9 MBeq/mmole), the chemical yield obtained was 55% while the radiochemical yield was 40%. The labelled compound produced was chemically as well as rediochemically pure. (author). 5 refs

[en] sup(99m)Tc-gluconate complex for renal imaging prepared by labeling of calcium gluconate solution appeared to show some radioactivity accumulated in the liver. For this reason, the use of gluconate complex prepared by tin(2) chloride reduction of sup(99m)TcO₄^- in sodium gluconate solution was investigated. The radiochemical analysis of the separated sup(99m)Tc-Sn-gluconate-(Na) complex was carried out by Whatman 1 paper chromatography using acetone and saline as the mobile phase. The biological distribution test in Swiss mice showed that the sup(99m)Tc-Sn-gluconate(Na) complex was well accumulated in the renal without significant accumulation in the lung or in the liver. Observation on human, both renal pathologically and clinically normal patient, proved that the complex has potential prospect for renal imaging. (author)

[en] The ⁹⁹Mo-^99mTc Chromatographic generators is the most popular system to provide ^99mTc medical radioisotope. Radioisotope Production Centre (RPC)- BATAN has routinely produced the generator loaded with ⁹⁹Mo prepared by ²³⁵U fission. By using fission produced ⁹⁹Mo, the resulting ^99mTc is potentially contaminated by other fission products which are difficult to eliminate completely. In order to study the characteristic of the generator and radionuclidic impurity pattern of the ^99mTc eluates, an evaluation of gamma spectrometric determination has been carried out. The bulk solutions of ⁹⁹Mo produced by RPC BATAN (Indonesia), Nordion (Canada) and ARI (Australia) were loaded to generators manufactured between July 1993 to May 1994. The saline-eluate ^99mTc, in a total volume of 10 ml each, was subjected to gamma spectrometric determination. The radiation of ^99mTc was eliminated by lead shield of 0.6913 cm thickness. The ^99mTc yield fluctuation from 28 generators indicated that the characteristics of the generator columns were very good. The ^99mTc eluates were consistently contaminated by ⁹⁹Mo, ¹³¹ I and ¹⁰³ Ru, although the contamination level in all cases did not exceed the maximum permissible levels. The fluctuation of radionuclidic impurities were probably caused by variation in the irradiation parameter or by variation in the ⁹⁹ Mo separation methods. (author), 23 refs, 1 tab, 3 figs

[en] The labelling of uracil (C₄H₄N₂O₂) with radioiodine (¹³¹I) have been carried out by means of reaction with iodomonochloride (¹³¹I). The analysis of the resulting iodinated compound was done using Whatman I paper chromatography and Silica Gel 60 F₂₅₄ thin-layer chromatography with a mixture of n-butanol-glacial acetic acid-water (75:30:50, v/v) as the eluting solvent. The result of UV spectrophotometric analysis strengthened the supposition that the labelling mechanism is an electrophilic substitution which gives 5-radioiodouracil as the resulting iodinated compound. The yield with the best labelling conditions was more than 97% so that purification of the iodinated compound was not necessary. It was observed that the final products were radiochemically stable after 8 days under ordinary storage conditions. (author). 8 refs

[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 use of radioactive preparation in Indonesia has sharply increased during the past years, indicated by increase of the number of companies utilizing radioisotopes during 1985 to 1999. It has been clearly stressed in the BATAN's Strategic Plan for 1994-2014 that the production of radioisotopes and radiopharmaceuticals is one of five main industrial fields within the platform of the Indonesian nuclear industry. Research programs supporting the production of radioisotopes and radiopharmaceuticals as well as development of production technology are undertaken by the Research Center for Nuclear Techniques (RCNT) in Bandung and by the Radioisotope Production Center (RPC) in Serpong, involving cooperation with other research center within BATAN, universities and hospitals as well as overseas nuclear research institution. The presented paper describes production and research status of radioisotopes and radiopharmaceuticals in Indonesia after the establishment of P.T. Batan Teknologi in 1996, a government company assigned for activities related to the commercial application of nuclear technology. The reviewed status is divided into two short periods, i.e. before and after the Chairman Decree No. 73/KA/IV/1999 declaring new BATAN organizational structure. Subsequent to the Decree, all commercial requests for radioisotopes and radiopharmaceuticals are fulfilled by P.T. Batan Teknologi, while demands on novel radioactive preparations or new processing technology, as well as research and development activities should be fulfilled by the Center for the Development of Radioisotopes and Radiopharmaceuticals (CDRR) through non-commercial arrangement. The near-future strategic research programs to response to dynamic public demand are also discussed. The status of research cooperation with JAERI (Japan) is also reported. (author)

[en] Capability of CeO₂ resin as chemical separator component and its immobilization potential to cadmium can be exploited for utilization of the resin in the separation of Cd-In matrices. The separation of Cd-In matrices is important for improving and mastering production technology of ¹¹¹/¹¹⁵m In using high-enriched ¹¹²/¹¹⁴ Cd targets. The phenomena on the sorption of Cd(11) on CeO₂ resin and its solvent elution pattern were studied using CeO₂ synthesized from reaction between Ce(SO₄)₂ and NH₄OH. A series of Cd(11) standard solution was treated with the activated resin in the both static and dynamic systems. The Cd(11) content of the solution after the treatment was the determined by UV-spectrophotometry for measuring Cd (11)-sorption capacity. The solvent elution pattern was observed by fractional elution from CeO₂ column followed by UV-spectrophotometric determination to the fractions giving positive test for Cd(11). It was found that the treatment of the resin with 10% NH₄OH solution increases the Cd(11)-sorption capacity of the resin compared to the treatment with water or 1M HCI solution. A sharp elution patter with quantitative yield of Cd(11) recovery (more than 94%) was found by elution using 5, 10 or 20% NH₄OH solution. Key words : CeO₂ resin, hydrous cerium oxide, radioisotope ¹¹¹/^115m In, separation of Cd-In matrices, sorption of Cd(11) on CeO₂ resin , elution profile of Cd(11) on CeO₂ resin, Cd(11) measurement by means of UV spectrophotometry

[en] Modification on labeling technique and chromatography mobile phase in the preparation and radiochemical analysis of ¹⁵³Sm-EDTMP. Preparation of ¹³⁵Sm-EDTMP. Preparation of ¹⁵³Sm-EDTMP for the therapy of metastatic bone cencer is carried out in CDRR-BATAN based on the reaction of ¹⁵³SmCl³ solution with EDTMP in phosphate buffer. Some disadvantages appear from the routine procedure, e.g. relatively lengthy radiochemical analysis, relatively low and fluctuative radioactivity yields, and potentially high radiation exposure and contamination risk to the operator and the working area. The present work is aimed at solving those problems. Radiochemical analysis using Whatman I-paper chromatography was performed in a variety of mobile phases consisting of one, two and three components, while the labeling technique was modified by changing the solvent for the EDTMP and by changing the reactant mixing procedure. It was proven that the of NH₄OH 25% - H₂O mixture (1 : 9, v/v) as the chromatographic solvent gave faster migration rate better chromatographic behaviour as compared to other mobile phases used in this experiment, including that is used in the routine procedure. The migration distance of 14 cm and 10 cm gave no significant difference on the radiochemical analysis results. The labeling technique by gradual addition of EDTMP in NaOH (pH 9 - 10) into ¹³⁵SmCl³ solution gave higher radioactivity yield and technically produced lower radiation exponsure and radioactive contamination risk as compared to the routine procedure. The proposed procedure is also better than the EDTMP labeling technique in acetic salt solution. The labeling efficiency achieved was highr than 98%, and therefore do not require any purification step. In general, the results of the present experiment gave good prospect to increase the efficiency and safety in the routine preparation process of ¹³⁵Sm-EDTMP

[en] Thallium-201 is a radioisotope widely used for visualization of heart or cardiovascular diagnosis. It is generally produced by means of ²⁰³Tl(p,3n)²⁰¹Pb -->²⁰¹Tl reaction using enriched ²⁰³Tl (more than 95%) as target material. Since the enriched ²⁰³Tl is very expensive, the recovery of ²⁰³Tl from ²⁰¹Tl-processing waste is very important. For this reason, a high accuracy and good precision method for Tl measurement is required. Having a single absorbance maximum at 214 nm which is stable up 24 hours post preparation, it is expected that Tl can be quantitatively determined by spectrophotometry in the UV region. The chemical matrices in the ²⁰¹Tl-processing waste were separated by hydroxide precipitation, stipping extraction and charcoal adsorption techniques. The linearity of the absorbance standard curve is given by regression line A = 0.0013 + 0.0223C with C is concentration in mg/dm³. The regression coefficient was found to be 0.9999. Evaluation using simulated waste solutions and ²⁰¹Tl-processing waste samples showed that both the accuracy and the precision, in terms of repeatability, of the measurement were high. (author)