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All Journal Pharmaciana: Jurnal Kefarmasian Jurnal Kimia Terapan Indonesia Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Adang Hardi Gunawan
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Biochemistry, Genetics & Molecular Biology Chemical Engineering, Chemistry & Bioengineering Chemistry Materials Science & Nanotechnology Medicine & Pharmacology

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Clearance profile of radioactive gold nanoparticle (198Au) conjugates-poliamidoamin generation 4-nimotuzumab ; potential radio-pharmaceutical theranostic agent Nurhatidjah Awaliyah Halid; Abdul Mutalib; Anung Pujiyanto; Adang Hardi Gunawan
Pharmaciana Vol 7, No 2 (2017): Pharmaciana
Publisher : Universitas Ahmad Dahlan

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (581.999 KB) | DOI: 10.12928/pharmaciana.v7i2.6725

Abstract

Theranostic agents are agents that combine diagnostic and therapeutic capabilities into a single agent. The presence of conjugated cancer which is therapeutic agents such as nimotuzumab monoclonal antibodies with radioactive gold nanoparticles stabilized with Polyamidoamine Generation 4 (PAMAM G4) dendrimer can actively interact with specific cancer cells. Radioactive gold (198Au) as a radiation transmitter β (961 keV) capable for killing cancer cells and (412 keV) γ rays that give a golden image in the body, thus acting as a theranostic agent. The purpose of this study was to obtain confident results of conjugate safety by observing the constituent clearance of 198AuNP-PAMAM G4-Nimotuzumab. The result of the conjugate clearance will be the reference for the metabolic state as a new, stable and complete radiofarmaka upon reaching the desired target. This study began with the synthesis of the conjugate of 198AuNp-PAMAM G4-nimotuzumab and then tested the clirens and analyzed the results of urine and mouse feces that had been injected with conjugate. Total clearance was obtained about 47.38% of the 198AuNP-PAMAM G4-Nimotuzumab conjugates that have been excreted through urine (18.26%) and stool (29.11%.). Urine and feces were analyzed with SDS-PAGE giving the spot above the 150 kDa band and showing the conjugate molecular weight. FTIR analysis of urine and feces by showing aldehyde functional groups (C = O), alcoholic groups (O-H), amine groups (C-N), and amine groups (N-H) indicating the presence of AuNP-PAMAM G4-Nimotuzumab conjugates in urine and mouse feces. The results of urine and fecal excretion of the conjugate are still conjugate-shaped supported by SDS PAGE analysis, UV-Vis spectrophotometer absorption analysis and functional group analysis with FTIR that has been conducted.
RADIONUCLIDIC IMPURITIES IN PERTECHNETATE SOLUTION ELUTED FROM 99mTc-CHROMATOGRAPHIC GENERATOR LOADED WITH 99Mo-FISSION PRODUCT Sunarhadijoso Soenarjo; Adang Hardi Gunawan
Jurnal Kimia Terapan Indonesia Vol 7, No 1-2 (1997)
Publisher : Research Center for Chemistry - LIPI

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (3245.144 KB) | DOI: 10.14203/jkti.v7i1-2.222

Abstract

Medical radioisotope of 99mTc was firstly produced in Indonesia through the nuclear reaction of 98Mo (n;y) 99Mo -> 99mTc. The separation of the resulting 99mTc from the postirradiated natural MoO3 was carried out by solvent extraction using methyl ethyl ketone. Instead of this method, Radioisotope Production Center (RPC) BATAN has routinely produced 99mTc-chromatographic generator loaded with 235U-flSsion-produced 99Mo to provide 99mTc. By such generator, 99mTc can be easily and repeatedly liberated in the form of pertechnetate by vacuum elution using saline solution. Some fission- produced radionuclides, however, potentially contaminate the pertechnetate fraction. Gamma spectrometric determination was carried out to evaluate the level of radionuclidic impurities contaminating 99mTc-pertechnetate solution eluted from 99mTc- chromatographic generator produced over a 10-month period in 1993 - 1994. Radioactivity yield of the resulting 99mTc was independent to the origin of the loaded 99Mo. The 99mTc-pertechnetatate fractions were frequently contaminated with 99Mo, 131I and 103Ru, but the contamination did not exceed maximum permissible level. The fluctuation of contamination level may be influenced by irradiation parameters and separation techniques applied to the production of the loaded 99Mo.
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.
PENENTUAN KEMURNIAN RADIOKIMIA 99mTc-MIBI SECARA CEPAT DAN PRAKTIS MENGGUNAKAN DOSE CALIBRATOR Maskur Maskur; Enny Lestari; Endang Sarmini; Yayan Tahyan; Amal Rezka Putra; Dede Kurniasih; Adang Hardi Gunawan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 1 (2017): 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.2017.23.1.3195

Abstract

Generally, the determination of radiochemical purity begins with Radiochemical separation using thin layer chromatography (TLC), and then measurement using a gamma counter, but this method cannot be applied in hospitals since there is only a dose calibrator available in the hospitals. Therefore, we conducted such an investigation using an alternative method which is more practical and faster, ie begins with radiochemical separation using extraction method, and then measurement using a dose calibrator. The determination was carried out in which 99mTc-MIBI was extracted using a mixture of saline and chloroform with volume ratio of 1:1, the mixture was then extracted. The 99mTc - MIBI was in organic phase (chloroform), whereas 99mTcO2 and 99mTcO4- were both in water phase (saline). Then, each phase of the sample was taken with the same volume, and then the radioactivity was measured using a gamma ionization chamber and the radiochemical purity was calculated. Radiochemical purity with extraction process method Compared measuring using standard methods of TLC Furthermore, the results of the extraction were compared with the standard method of TDC. The results showed that the radiochemical purity of 99mTc-MIBI using the two methods were almost the same, ie =98.34 % ± 0, 65 % for TLC standard method and = 97.15 % ± 0,56 % for extraction method with good measurement precision. The time of determination for extraction method was 20 minutes and 180 minutes for TLC standard method respectively. These results indicated that the extraction method can be used as an alternative method for determination of radiochemical purity of 99mTc-MIBI radiopharmaceutical. The advantage of extraction method that it is faster compared to the TLC Method.
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 Abdul Mutalib Amal Rezka Putra Anung Pujiyanto Chairuman Dede Kurniasih Endang Sarmini Enny Lestari Gatot Setiawan Maskur Maskur Nur Hatidjah Awaliyah Halid Sulaiman Sunarhadijoso Soenarjo WIDYASTUTI Yayan Tahyan Yono Sugiharto