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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Yono Sugiharto
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OPTIMASI PH ALUMINA DAN 99Mo DALAM PEMBUATAN GENERATOR 99Mo/99mTc BERBASIS MoO3 ALAM Sulaiman; Yono Sugiharto; Chairuman; Gatot Setiawan; Adang Hardi Gunawan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (2018): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2018.24.2.4159

Abstract

Alumina material has long been used for 99Mo radioisotope adsorbent in the 99Mo/99mTc generator. The 99Mo/99mTc generator produces 99mTc radioisotope which is used for the diagnostic purposein nuclear medicine. To date, alumina is used to adsorp 99Mo obtained from fission reaction of 235U. The restriction of the use of fission 235U leads to the find of an alternative 99Mo. The alternative of 99Mo production is obtained from natural MoO3 which is irradiated by thermal neutron in the nuclear reactor. The 99Mo radioisotope produced from this reaction has no carrier-free properties. This is due to the abundanceof natural MoO3 is 24.13%.In the99Mo/99mTc generator based on natural MoO3 by using alumina column, it is necessary to know the alumina type for optimum 99Mo adsorption, as well as pH of 99Mo. In this study, there were used three variations of alumina-based generator column namely acid, neutral, and basic alumina. The 99Mo solution used in this study was also performed three pH: pH 4, pH 7, and pH 8 of the 99Mo solution. The generator eluted and observed daily for 3 days and continued after the next two days for 2 days. The optimum adsorption of 99Mo from natural MoO3 by alumina material was given in the use of acidic alumina with the pH 4 of the99Mo solution. Among the three pH variation of the 99Mo solution, the 99Mo solution of pH 4 gives the highest of 99mTc yield. The column with the smallest 99Mo breakthrough is given by acidic alumina column using the 99Mo solution of pH 4. Thus, acidic alumina column can be used as an adsorbent to adsorp natural 99Mo.
PEMBUATAN SENYAWA BERTANDA 131I-MIBG DENGAN PENINGKATAN DOSIS TERAPI Maskur Maskur; Chairuman; Yono Sugiharto; Khoirunnisa Fauziah Asyikin; Triningsih; Sulaiman
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 1 (2021): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.1.6358

Abstract

Nowadays, the labeled compound of 131I-MIBG has been successfully produced in Indonesia. However, the concentration of radioactivity and dose of radioactivity per vial is still small when compared to commercial products from abroad available in the market. Currently, the dose of radioactivity achieved is 25 mCi/vial with a concentration of 5 mCi/mL. Problems arise if the radioactivity and dose of radioactivity per bottle are enlarged, where the product becomes unstable and breaks down because of the effects of radiolysis. The generally global commercial products contain a dose of radioactivity = 100 mCi/vial with a concentration of 10 mCi/mL. By this research efforts have been made to increase the concentration and dose of radioactivity per bottle. The method used was by increasing the amount of benzyl alcohol from 9 μL/mL to 10 μL/mL of 131I-MIBG solution. Other than that, the addition of phosphate buffer which was originally added before the purification process was switched to after the purification process. The result of labeling was 131I-MIBG 153 - 254 mCi with process yield between 33.60 and 51.94%. The radioactivity concentration was quite large, i.e., between 9.80 to 25.40 mCi/mL with radioactivity doses ranging from 100 to 222 mCi/vial. However, to adjust to market needs, the I-MIBG of Batan product was then packaged in 100 mCi/vial with a concentration of 5-13 mCi/mL.This workaround shows that the synthesis of labeled compound of 131I-MIBG for scale up therapeutic dose has been successfully carried out.
PENGARUH REGENERASI KOLOM ALUMINA ASAM TERHADAP RECOVERY DAN KUALITAS 99mTc HASIL EKSTRAKSI PELARUT MEK DARI 99Mo HASIL AKTIVASI NEUTRON Adang Hardi Gunawan; Yono Sugiharto; Widyastuti
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2016.22.3.3186

Abstract

Purification of 99mTc from 99Mo activation using acidic alumina column chromatography system from MEK (Methyl Ethyl Keton) extraction has been carried out through cooperation between PTRR - BATAN, Chiyoda and JAEA Japan. This method has a limitation that acidic alumina column for purification of 99mTc can be used only once, for the next purification acidic alumina column should be replaced with new column, so it is less practical and also requires high cost. This study aims to obtain a 99mTc solution can be used for labelling of a radiopharmaceutical kit. In this study, the used of acidic alumina column for 99mTc purification was tried more than once by regeneration using 0.1N HNO3 solution after purification process is completed. Parameters observed in this study are the percent recovery, elution profile, pH, radiochemical purity and radionuclide purity. The results of observational studies conducted over 5 days has been obtained pH ~ 5, % recovery > 60%, radiochemical purity of > 95% and 99Mo leakage not detected. The treatment of acidic alumina column with 0,1 N HNO3 solution concluded that acidic alumina column does not need to be replaced every day.
Co-Authors Adang Hardi Gunawan Chairuman Gatot Setiawan Khoirunnisa Fauziah Asyikin Maskur Maskur Sulaiman Triningsih WIDYASTUTI