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All Journal Indonesian Journal of Pharmaceutical Science and Technology Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Endang Sarmini
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Computer Science & IT Medicine & Pharmacology

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Preliminary Study on Production Of 32P – Labeled Phosphate Chromic as A Material for Skin Patch Wira Y. Rahman; Endang Sarmini; Herlina Herlina; Abidin Abidin; Triyanto Triyanto; Hambali Hambali; Sriyono Sriyono; Triani Widyaningrum
Indonesian Journal of Pharmaceutical Science and Technology Suppl. 2, No. 3 (2019)
Publisher : Indonesian Journal of Pharmaceutical Science and Technology

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (508.919 KB) | DOI: 10.24198/ijpst.v1i3.20982

Abstract

Keloids are skin disorders or benign tumours that are due to abnormal wound healing in the binding tissue after a trauma, inflammation, surgical wounds, or burns. Low activity radioisotopes have shown to be effective in curing or eliminating keloids on the skin. One of these radioisotopes is phosphorus-32 (32P), a beta (β-) emitter with a half-life of 14.3 days. This radioisotope can also be developed for the treatment of keloid and skin tumours. Currently, keloid is treated by a conventional method e.g.by applying the bulk of 32P radioisotope directly on keloid area. However, this method is considered inefficient and less secure. The purpose of this research is to obtain a technology for preparing of 32P-labeled skin patch. The first step of this research is to produce 32P-labeled chromic phosphate (Cr32PO4) colloids, through condensation involving oxidation-reduction reaction. In this step, Cr (VI) is reduced to Cr (III) to form Cr32PO4 with particle size of <1 μm.  These particles (Cr32PO4) are to expect to distribute evenly when mixed with silicon to form skin patch which will not decompose easily. Characterization of the prepared Cr32PO4colloids gave a yield of 97,8% with particle size of greater than > 1μm.  Further study needs to be performed in due time in order to have Cr32PO4 colloids with a suitable particle size.Key words: keloid, chromic phosphate colloid, skin patch, condensation, oxidation-reduction reaction
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.
PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc) Indra Saptiama; Herlina; Sriyono; Endang Sarmini; Abidin; Kadarisman
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 2 (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.2016.22.2.3094

Abstract

Uranium usage restriction causes the hospitals in Indonesia difficult to obtain the supply of 99mTc. At Present, 99mTc is obtained from molybdenum as a uranium fission product. Production of 99Mo radionuclide resulted from neutron activated natural molybdenum (MoO3) in G.A Siwabessy reactor could be used as an alternative method for producing 99mTc. The aim of this research is synthesized of 99Mo radionuclide from neutron activated natural molybdenum (MoO3) to obtain 99mTc. The five grams of MoO3 powder was packed in a quartz ampule and inserted into inner capsule then also inserted into outer capsule as a target material. It was irradiated in G.A Siwabessy reactor for 100hours. Based on theoritical calculation, about 65 % of maximum 99Mo activity could be recovered. After irradiation, MoO3 was dissolved by NaOH 4 M solution, so it was natrium molybdate (Na2MoO4) solution. 99Mo and 99mTc radionuclide were analyzed using gamma spectrometer. 99Mo radionuclide was detected on Na2MoO4 solution as product that had specific activity of 0.81 Ci 99Mo/ g Mo. 99mTc as daughter radionuclide was separated from 99Mo as parent radionuclide using separated column containing zirconium-based material (ZBM) as 99Mo adsorbent. 99mTc radionuclide has been successfully separated using ZBM column although recovery of 99mTc was quite low in which approximately 52 to 71 %. The 99mTc radionuclide was recovered in the form of sodium pertechnetate (NaTcO4) solution.
Co-Authors Abidin Abidin Abidin Adang Hardi Gunawan Amal Rezka Putra Dede Kurniasih Enny Lestari Hambali Hambali Herlina Herlina Herlina Indra Saptiama Kadarisman Maskur Maskur Sriyono Sriyono Sriyono Triani Widyaningrum Triyanto Triyanto Wira Y. Rahman Yayan Tahyan