Tc generator Neutron activated Mo ZBM 99mTc Molybdenum produced from fission of U-235 is the most desirable precursor for 99 Mo/ 99m Tc generator system as it is non-carrier added and has high specific activity. However, in the last decade there has been short supply of Tc required for medical purposes.

The present study deals with the synthesis and characterization of ZrO 2 nanomaterial which can be used as an adsorbent for Molybdenum-99 ( 99 Mo).The adsorbent can potentially be utilized as the material for 99 Mo/ 99m Tc generator column. Using the sol-gel method, monoclinic nanocrystalline zirconia was synthesized from zirconium oxychloride in isopropyl alcohol reacted with ammonium hydroxide solution in isopropyl alcohol resulting in a white gel. The gel was subsequently refluxed for 12 hours at ~95 °C and pH at ~4 and then dried at 100 °C. The drying gel was then calcined at 600 °C for two hours. Meanwhile the orthorhombic nanocrystalline zirconia was obtained by reacting zirconium oxychloride solution with 2.5 M ammonium hydroxide solution which resulted in a white gel. The gel was then refluxed for 24 hours at ~95 °C and pH at ~11 and then dried at 100 °C. The drying gel was then calcined at 600 °C for two hours. These materials were characterized using FT-IR spectroscopy, X-ray diffraction (XRD), and Transmission Electron Microscope (TEM). The Scherrer method is used for determination of crystallite size. The FT-IR spectra for both materials show absorption peak at 450-500 cm -1 which are attributed to Zr-O bond. The XRD pattern of monoclinic nanocrystalline form shows crystalline peaks at 2θ regions of 28.37 °, 31.65 °, 34 °, 36 ° and 50.3 ° with average crystallite size of 2.68 nm. Meanwhile, the XRD pattern of orthorhombic nanocrystalline form shows crystalline peaks at 2θ regions of 30 °, 35 °, 50 ° and 60 ° with average crystallite size of 0.98 nm. The TEM micrograph indicates that the zirconia nanomaterials prepared were quite uniform in size and shape.

]molybdate was then packed into generator column, then eluted with 10 × 1 mL of saline followed by 1 × 5 mL of NaOCl solution. The NaOCl solution concentrations used were 0.5%; 1%; 3%; and 5% for each column, respectively. This study resulted in a ZBM which has a 99 Mo adsorption capacity of 167.5 ± 3.4 mgMo/g ZBM, as well as in a yield eluate of 99m Tc of up to 70%, and the find that the optimum NaOCl concentration was 3%. The use of sodium hypochlorite solution affected 99 Mo breakthrough. The higher sodium hypochlorite concentration used, the more 99 Mo breaktrough exist on 99m Tc eluate.

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc). Pembatasan penggunaan uranium sebagai target untuk produksi 99mTc menyebabkan rumah sakit di Indonesia  kesulitan mendapatkan pasokan 99mTc. Saat ini 99mTc diperoleh dari 99Mo hasil fisi (pembelahan uranium).  Pembuatan radionuklida 99Mo dari aktivasi neutron  molibdenum alam (MoO3) di teras reaktor G.A Siwabessy digunakan sebagai metode alternatif untuk memperoleh 99mTc. Tujuan penelitian ini adalah untuk melakukan pembuatan radionuklida 99Mo dari aktivasi neutron molibdenum alam untuk memperoleh 99mTc. Serbuk MoO3 alam sebanyak 5 gram dikemas dalam ampul kuarsa dan dimasukkan ke dalam inner capsul selanjutnya dikemas menggunakan outer capsul sebagai bahan target. Bahan target diiradiasi di reaktor G.A Siwabessy selama 100 jam. Hasil perhitungan diperoleh aktivitas  99Mo sebesar 65 % dari nilai maksimum yang dapat diperoleh. MoO3 paska iradiasi dilarutkan dengan NaOH 4 M sehingga diperoleh larutan natrium molibdat (Na2MoO4). Radionuklida 99Mo dan 99mTc diukur menggunakan spektrometer gamma. Radionuklida 99Mo terdeteksi dalam produk larutan  Na2MoO4 dengan  aktivitas jenis 99Mo yang diperoleh sebesar 0,81 Ci 99Mo/g Mo.  Radionuklida anak luruh 99mTc dipisahkan dari radionuklida induk 99Mo menggunakan kolom pemisah yang berisi material berbasis zirkonium (MBZ) sebagai penyerap 99Mo. Radionuklida 99mTc hasil pemisahan diperoleh dalam bentuk natrium pertehnetat (Na99mTcO4).dengan recovery yang masih rendah yaitu sekitar 52 hingga 71 %.Kata kunci: Molibdenum, teknesium, radionuklida, pemisahan, iradiasi. PRODUCTION OF ACTIVATED  NEUTRON MOLYBDENUM-99 (99Mo) RADIONUCLIDE FROM NATURAL MOLYBDENUM TO OBTAIN TECHNETIUM-99m (99mTc).  Uranium usage restriction causes the hospitals in indonesia difficult to obtain the suply of  99mTc. At Present, 99mTc is obtanied 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 a alternatif method for producing 99mTc. The aim of this research is synthesize 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 iradiated 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 adsobent. 99mTc radionuclide has been succesfully 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.Keywords: Molybdenum, technetium, radionuclide, separation, irradiation.

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Penentuan Kemurnian Radiokimia 99mTc-MIBI dengan Cepat Dan Praktis menggunakan Metoda Ekstraksi. Pengujian radiokimia umumnya menggunakan metoda kromatografi lapis tipis (KLT), akan tetapi memerlukan waktu pengujian lama. Oleh karena itu, perlu alternatif menggunakan metoda ekstraksi yang lebih praktis dan cepat. Pengujian dilakukan dengan cara 99mTc-MIBI diekstraksi menggunakan campuran salin dan chloroform dengan perbandingan volume = 1:1.  Campuran diekstraksi sehingga terpisah antara 99mTc-MIBI dan pengotornya, yaitu 99mTc-MIBI dalam fasa organik (Chloroform) sedangkan 99mTcO2 dan 99mTcO4- keduanya dalam fasa air (salin). Kemudian, masing-masing dicuplik dengan volume yang sama dan diukur radioaktivitasnya menggunakan Gamma Ionisation Chamber dan dihitung kemurnian radiokimianya. Hasil ekstraksi dibandingkan dengan pengujian menggunakan metoda baku KLT. Hasil penelitian menunjukkan bahwa pengujian radiokimia  kit 99mTc-MIBI menggunakan kedua metoda tersebut hasilnya hampir sama, yaitu =98,34%±0,65 (metoda baku KLT) dan 97,15%±0,56 (metode ekstraksi) dengan kepresisian pengukuran yang baik, yaitu RSD <1% (RSD metode baku KLT=0,65% dan metode ekstraksi 0,56%). Waktu pengujian yang diperlukan dengan metoda ekstraksi = 20 menit  dan metoda baku KLT =180 menit. Hasil ini menunjukkan bahwa metoda ekstraksi dapat digunakan sebagai alternatif dalam pengujian radiokimia kit MIBI. Keunggulan metoda ekstraksi adalah waktu pengujian lebih cepat dibandingkan metoda KLT.Kata kunci : Kemurnian Radiokimia, 99mTc-MIBI, metoda ekstraksi, metoda Kromatografi Lapis Tipis

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