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EVALUASI PROSES PRODUKSI RADIOISOTOP Sm-153 DAN SEDIAAN RADIOFARMAKA Sm-153 EDTMP Kadarisman, Kadarisman; Hastini, Sri; Tahyan, Yayan; Abidin, Abidin; Hafid, Dadang; Lestari, Enny
Jurnal Radioisotop dan Radiofarmaka Vol 9 (2006): jurnal PRR 2006
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

EVALUASI PROSES PRODUKSI RADIOISOTOP Sm-153 DAN SED1AAN RADIOFARMAKA Sm-153 EDTMP. Telah dilakukan percobaan proses produksi radioisotop Sm-153 dan proses penandaan sediaan radiofarmaka Sm-153 EDTMP, yang bertujuan untuk mengevaluasi proses produksi radioisotop Sm-153 dan sediaan radiofarmaka Sm-153 EDTMP di Pusat Radioisotop dan Radiofarmaka, BATAN. Dalam percobaan ini mencakup penyiapan bahan sasaran Sm2O3, pelarutan pasca irradiasi, penetapan konsentrasi radioaktivitas isotop Sm-153, kemurnian radionuklida, proses penandaan senyawa EDTMP, penetapan kemurnian radiokimia dan pH. Dalam percobaan ini diperoleh produk radioisotop Sm-153 dengan radioaktivitas total antara 2845,83 mCi s/d 36963,31 mCi atau dengan konsentrasi radioaktivitas antara 474,30 mCi/ml sampai dengan 6160,55 mCi/ml) berbentuk larutan SmCl3yang masing-masing mempunyai volume 6,0 ml, kandungan samarium 5,76 mg/ml dan dengan kemurnian radionuklida dari produk radioisotop Sm-153 adalah 100 %. Semua produk sediaan radiofarmaka Sm-153 EDTMP memenuhi syarat konsentrasi radioaktivitas, kandungan Sm, kemurnian radiokimia dan pH. Konsentrasi radioaktivitas sediaan radiofarmaka Sm-153 EDTMP minimum 37,50 mCi/ml dan yang terbesar 283,50 mCi/ml, sebanyak 8 buah larutan mempunyai pH 7,5, sedangkan yang lainnya ( 2 buah larutan ) mempunyai pH sebesar 8,5. Kemurnian radiokimia sediaan raiofarmaka Sm-153 EDTMP berkisar antara 90,00 % sampai dengan 98,76 %. Kata Kunci : Evaluasi, Radioisotop, Radiofarmaka, Sm-153, Sm-153 EDTMP EVALUATION OF RADIOISOTOPE PRODUCTION PROCESS OF Sm-153 AND Sm-153 EDTMP RADIOPHARMACEUTICALS. Experiments on the process of Sm-153 radioisotope and labeling of Sm-153 EDTMP radiopharmaceuticals were carried out, as a purpose for evaluation of Sm-153 radioisotope and Sm-153 EDTMP process production in Center for Radioisotope and Radiopharmaceuticals, National Nuclear Energy Agency. This experiments included preparation of Sm2O3target, dissolution of post irradiation, determination of radioactivity concentration of Sm-153 radioisotope, radionuclide purity, EDTMP labeling, determination of radiochemicals purity and pH. In these experiments the total radioactivity Sm-153 product is about 2845.83 mCi to 36963,31 mCi, or with the radioactivity concentration between 474,30 mCi/ml and 6160,55 mCi/ml in the SmCl3solution form. The volume is 6.0 ml, the samarium content is 5.76 mg/ml and the radionuclide purity of Sm-153 is 100 %. All of the Sm-153 EDTMP radiopharmaceuticals product are fullfilled requirements the radioactivity concentration, Sm content, radiochemical purity and pH. The radioactivity concentration of Sm-153 EDTMP radiopharmaceuticals is 37,50 mCi/ml(minimum) to 283,50 mCi/ml (highest). The pH 7.5 were 8 products, and the rest are pH 8.5. Radiochemical purity of Sm-153 EDTMP are round about 90.00 % to 98,76 %. Key Words : evaluation, radioisotope, radiopharmaceutical, Sm-153, Sm-153 EDTMP
OPTIMASI KONDISI SPEKTROMETER ALFA DENGAN DETEKTOR ION-IMPLATED SILIKON DI PUSAT PRODUKSI RADIOISOTOP Kadarisman, Kadarisman; Mutalib, Abdul; Gunawan, Adang Hardi; Lubis, Hotman; Lestari, Enny; Mujinah, Mujinah; Hafid, Dadang
Jurnal Radioisotop dan Radiofarmaka Vol 1, No 1 (1998): Jurnal PRR 1998
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

OPTIMASI KONDISI SPEKTROMETER ALFA DENGAN DETEKTOR ION­IMPLATED SILIKON DI PUSAT PRODUKSI RADIOISOTOP. Telah dilakukan penetapan kondisi optimum spektrometer alfa yang dibubungkan dengan detektor silikon yang diimplantasi ion dengan standar sumber radiasi alfa campuran 239Pu, 241Am dan 244Cm.Pengamatan meliputi penetapan jarak antara cuplikan dengan detektor, tingkat kevakuman, batas deteksi alat dan penetapan efisiensi pencacahan dari masing-masing radionuklida. Dari percobaan diperoleh hasil kondisi optimum yaitu, jarak antara detektor dengan standar 1- 2 cm, tekanan kevakuman -1050 mbar, batas deteksi 5,1 dpm dan efisiensi pencacahan masing-masing untuk 239Pu (5157 keV) 10.6%, 241Am(5486 keV) 10,3% dan 244Cm(5805 keV) 9,9%. OPTIMIZATION OF ALPHA SPECTROMETER COUPLED TO ION-IMPLANTED SILICON DETECTOR IN RADIOISOTOPE PRODUCTION CENTER. The optimization of alpha spectrometer coupled to an ion-implanted silicon detector was carried out using an alpha radiation mixed standard source containing radionuclides of 239Pu, 241Am and 244Cm. This experiment involved the determination of the optimum distance between a radiation source and the detector surface, the pressure of the vacuum chamber, and the detection limit and the efficiency of the detector. The results show that the optimum distance between the radiation source and the detector is 1-2 cm; the pressure is -1050 mbar; the detection limit is 5.1 dpm, and the efficiencies for 239Pu ( 5157 keV), 24lAm (5486 keV) and 244Cm(5805 keV) are 10.6%, 10.3% and 9.9%, respectively.
DEVELOPMENT OF NOVEL ALUMINA BY SOLID-STATE REACTION FOR 99MO/99MTC ADSORBENT MATERIAL Munir, Miftakul; Lestari, Enny; Hambali, Hambali; Kadarisman, Kadarisman; Marlina, Marlina
Al-Kimia Vol 7, No 2 (2019): DECEMBER
Publisher : Study Program of Chemistry - Alauddin State Islamic University of Makassar

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (527.851 KB) | DOI: 10.24252/al-kimia.v7i2.9123

Abstract

Technetium-99m (99mTc), a daughter radionuclide of molybdenum-99 (99Mo), is the most widely used radiodiagnostic agent due to its ideal characteristics. The separation of this radionuclide from 99Mo is commonly performed using alumina. However, a new production method of this radionuclide, which employs a low specific activity 99Mo, makes alumina no longer suitable as separation material. This study aims to develop novel alumina using a facile solid-state reaction for 99Mo/99mTc generator system. The SS-alumina was synthesized from aluminium nitrate nonahydrate and ammonium bicarbonate without solvent. The resulted SS-alumina was then analyzed by FTIR and BET method. 99Mo adsorption and 99mTc releasing study on a series of pH were also performed. FTIR study revealed that the resulting material was Al2O3 with a surface area of 237.65 m2/g. The adsorption capacity, 99mTc yield, 99Mo breakthrough, and alumina breakthrough were 76.06 mg Mo/g alumina, 80.31%, 56.5 µCi/mCi 99mTc, and less than 5 mg/mL, respectively. The elution profile shows a high activity of 99mTc in 2nd and 3rd fraction. It is concluded that the SS-alumina shows good performance as adsorbent material for separation of a 99Mo/99mTc and further work is now underway.
KEPEMIMPINAN INOVATIF DALAM UPAYA MENINGKATKAN PELAYANAN PUBLIKDI KECAMATAN KOTA SUMENEP Ghufrony, Ahmad; Kadarisman, Kadarisman
PERFORMANCE: Jurnal Bisnis & Akuntansi Vol 8 No 1 (2018): Jurnal Performance "Bisnis dan Akuntansi"
Publisher : Fakultas Ekonomi dan Bisnis

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (187.711 KB) | DOI: 10.24929/feb.v8i1.468

Abstract

Inovatif behaviour is often related to creativities. Both of it is true, butbehavioral construct of creativity and inovatif have various difference. Its impactalmost at all of life area, do not aside from governance sector and also of publicorganisation applied by a leader specially District of Town of Sumenep. Focus ofthis research which will reach that is " to know leader of inovatif in the effortimproving service of public in Kecamatan Kota Sub-Province of Sumenep". Datawich used is primary data and of sekunder. Research subyek that is using keyinforman. Was gathered, hence technique analyse data conducted step by step:data reduction, presentation of phase and data of take a summary later;then alsodone authenticity of data. Conclusion of this research oriented its intention dutyof consistency of style or leader attitude of inovatif to improve service of public,relation orienting that is owning ability manage or construct officer in officedistrict of town in finishing work and also oriented change that meant by repair ofstrategic decision to environmental behavior, making change specially processarea, product, service, and its comitment.
Stability of Silver Nanoparticles as Imaging Materials Sholikhah, Umi Nur; Pujiyanto, Anung; Lestari, Enny; Sarmini, Endang; Widyaningrum, Triani; Kadarisman, Kadarisman; Triyanto, Triyanto; Puspitasari, Putri
The Journal of Pure and Applied Chemistry Research Vol 5, No 3 (2016)
Publisher : Chemistry Department, The University of Brawijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (655.071 KB) | DOI: 10.21776/ub.jpacr.2016.005.03.295

Abstract

Determining the stability of silver nanoparticles is a very important process. It was associated with unwanted metal charge and materials properties. Therefore, we studied to synthesis and stability of silver nanoparticles (AgNPs). The synthesis was performed by reduction method used sodium borohydride (NaBH4). Silver nitrate solution 0.0005 M in 1 mL was reduced using 1 mL 0.002 M of NaBH4. Then a 40.0 mL of polyvinylpyrrolidone 0.3% and 20 mL of 1.5 N NaCl was added to the mixture. Characterization of silver nanoparticles is undertaken using spectrophotometer UV-Vis, transmission electron microscopy, particle size analyzer and zeta potential. The stability of products is observed for 5 times using spectrophotometer UV-Vis. The product was characterized by determining its surface plasmon resonance (SPR) of AgNPs and the result was obtained at 403 nm. The size of AgNPs was 20 nm using tomography emission microscopy analysis and the particle size distribution give 5.8 nm. The dielectric charge was 53 mV. The stable AgNPs showed no significant SPR shift at 402±0.89 nm wavelength during 5 days observation. Based on the size and stability, it was suitable for imaging materials.
Desain dan Performa Prototipe Generator 99Mo/99mTc dengan Kolom Material Berbasis Zirkonium dan Kolom Alumina Marlina, Marlina; Sriyono, Sriyono; Lestari, E.; Abidin, Abidin; Setiawan, H.; Kadarisman, Kadarisman
Jurnal Kimia dan Kemasan Vol. 38 No. 2 Oktober 2016
Publisher : Balai Besar Kimia dan Kemasan

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1854.602 KB) | DOI: 10.24817/jkk.v38i2.2703

Abstract

Hingga saat ini radioisotop tehnesium-99m (99mTc) masih banyak digunakan di bidang kedokteran nuklir di seluruh dunia. Hal ini karena 99mTc memiliki waktu paro 6 jam dan memancarkan gamma murni pada energi 140 keV sehingga merupakan radioisotop yang ideal untuk diagnosis. 99mTc dapat dihasilkan salah satunya dari generator 99Mo/99mTc. Prototipe generator 99Mo/99mTc dibuat dengan menggunakan Molibdenum-98 (98Mo) alam hasil iradiasi neutron, yang dilengkapi dengan kolom berisi material berbasis zirkonium (MBZ) dan kolom alumina. Penentuan performa prototipe generator dilakukan dengan menentukan yield 99mTc, kualitas larutan natrium pertehnetat (Na99mTcO4) yang dihasilkan, dan laju dosis pada permukaan prototipe generator. Yield 99mTc dari prototipe generator yaitu 76,95 ± 7,7%. Prototipe generator menghasilkan radioisotop 99mTc (Na99mTcO4) dengan karakterisitik yang memenuhi persyaratan US Pharmacopoeia, yaitu larutan jernih, memiliki pH 6 ± 0,6, kemurnian radionuklida (lolosan 99Mo) sebesar 0,022 μCi/mCi 99mTc, kemurnian radiokimia 99mTcO4- sebesar 99,85 ± 0,05%, kemurnian kimia (lolosan alumina) < 5 μg/mL, dan laju dosis permukaan prototipe sebesar 1,18 mSv/jam. Dengan demikian prototipe generator 99Mo/99mTc ini sudah menunjukkan performa yang baik dalam menghasilkan radioisotop 99mTc untuk keperluan medis dan memiliki laju dosis yang aman, namun perlu ditingkatkan kembali yieldnya. 
PEMISAHAN FRAKSI OSMIUM DAN IRIDIUM DALAM MATRIKS OSMIUM ALAM PASCA IRADIASI DENGAN TEKNIK EKSTRAKSI PELARUT Kadarisman, Kadarisman; Lubis, Hotman; Sriyono, Sriyono; Abidin, Abidin
Jurnal Radioisotop dan Radiofarmaka Vol 10 (2007): JURNAL PRR 2007
Publisher : Jurnal Radioisotop dan Radiofarmaka

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PEMISAHAN FRAKSI OSMIUM DAN IRIDIUM DALAM MATRIKS OSMIUM ALAM PASCA IRADIASI DENGAN TEKNIK EKSTRAKSI PELARUT. Generator Osmium – Iridium ada dua macam, yaitu generator radioisotop 191Os – 191mIr dan 194Os – 194Ir. Radioisotop 191mIr dan 194Ir digunakan di bidang kesehatan, terutama untuk diagnosis fungsi ginjal dengan metoda Angiografi. Dalam penelitian ini dilakukan pemisahan 191Os dari 192Ir melalui tahapan tahapan penelitian; penyiapan target Osmium alam, iradiasi target, perlakuan target teriradiasi, yang meliputi pengangkutan target teriradiasi ke fasilitas hot cell, pembukaan tabung dan pelarutan, serta proses pemisahan Osmium teriradiasi dengan ekstraksi pelarut menggunakan CCl4. Analisis radionuklida 191Os dan 192Ir menggunakan spektrometer gama. Dari hasil percobaan ini diperoleh radionuklida 191Os dan 192Ir dalam Osmium alam teriradiasi masing-masing sebesar 87,88 µCi dan 20,01 µCi saat pemisahan. Radionuklida 191Os dapat dipisahkan dari pengotor radionuklida 192Ir dengan radioaktivitas total 14,83 µCi dengan efisiensi pemisahan sebesar 16,88% pada akhir pemisahan. Hal ini menunjukkan kemungkinan dapat dipreparasi radionuklida 191Os atau 194Os untuk bahan generator 191Os/191mIr dan 194Os/194Ir. Kata Kunci : Osmium-191, Iridium-192, Ekstraksi, Generator 191Os/191mIr atau 194Os/194Ir THE SEPARATION OF FRACTION OF OSMIUM AND IRIDIUM IN OSMIUM MATRIX IRRADIATED WITH THE EXTRACTION LIQUID TECHNIQUE. Generator Osmium - Iridium there is 2 kinds of, that is radioisotope generator 191Os/191mIr dan 194Os/194Ir. Radioisotope 191mIr and 194Ir used in health area, especially to be diagnosed to a kidney function with the Angiography method. In this development conducted separation 191Os from 192Ir through research step; experienced Osmium target preparation, target irradiation, treatment of target irradiated, covering the transportation of target irradiated to facility of hot cell, opening save and dissolution, and also separation process of Osmium irradiated by solvent extraction use the CCL4. Analysis the radionuclide of 191Os and 192Ir use the gamma spectrometer. From this attempt result is obtained 191Os and 192Ir in Osmium irradiated each of 87,88 µCi and 20,01 µCi of dissolution moment. Radionuclide 191Os is detachable from 192Ir radionuclide impurities with the total radioactivity 14,83 µCi with the dissolution efficiency of equal to 16,88% by the end of dissolution. This matter show the possibility earn the preparation radionuclide 191Os atau 194Os for the substance of generator 191Os/191mIr or 194Os/194Ir. Keywords : Osmium-191, Iridium-192, Extraction, 191Os/191mIr or 194Os/194Ir Generator.
PELATLHAN PROGRAM INKUBATOR BISNIS DI SEKOLAH MENENGAH UMUM NEGERI KALASAN SLEMAN TAHAP I Priyanto, Priyanto; Kadarisman, Kadarisman; Utomo, Pramudi
INOTEKS Vol 1, No 2 (2000): Januari 2000
Publisher : LPPM UNY

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Abstract

Kegiatan  pen gab dian  kepada  masyarakat   yang  merupakan   Pelatihan   Program  Inkubator   Bisnis  ini diperuntukkan    bagi siswa-siswa  SMUN Kalasan  yang tahun  ini merupakan  tahun (tahap)  pertama.  Secara umum tujuan  yang ingin dicapai  dengan program  ini adalah  bahwa  setelah  peserta  selesai mengikuti  kegiatan  sampai  dengan  tahap  III, peserta  memiliki  pengetahuan, kemampuan  dan keterampilan  untuk memelihara,  merawat,  dan memperbaiki  komputer,  Dengan pengetahuan,   kemampuan  dan keterampilan  yang dimiliki tersebut  diharapkan  mereka  dapat hidup mandiri,  menggunakan   kemampuan  dan  keterampilannya untuk   berwirausaha     sehingga    dapat   dimanfaatkan    untuk   menopang    kehidupan    keluarganya,     atau  paling   tidak   untuk meningkatkan   taraf  hidupnya,   Secara  khusus  tujuan  yang  ingin  dicapai  pad a kegiatan  tahap  awal  ini  adalah  para  peserta memiliki   pengetahuan    dan  kemampuan   dasar  tentang   komputer   yang  meliputi   bagian-bagian    beserta   fungsi  dan  prinsip kerjanya. Metode   yang  digunakan   dalam  rangka  pelaksanaan    program   inkubator   bisnis   di  SMU  Kalasan   ini  adalah   dengan menggunakan  pendekatan  teori dan praktek. Teori diberikan sebelum praktek. Dalam menyampaikan  teori, pengabdi menunjukkan komponen-komponen     yang  dijelaskan   beserta  prinsip  kerjanya.  Disamping   itu peserta  memberikan   penjelasan   singkat  apa dan bagaimana  komputer  bisa bekerja.  Dalam  kegiatan  praktek,  peserta  dibimbing  agar berani  mencoba,   dengan  asumsi jika keberanian   telah ada dihati  perserta  maka untuk melaksanakan   praktek  akan dapat berjalan  dengan  lancar. Hasil  dari  kegiatan  ini adalah  telah  berhasil  dilakukan  pelatihan   dengan   dengan  materi  perawatan,   pemeliharaan    dan perbaikan  komputer  yang  sifatnya  masih  sangat  dasar. Materi  yang telah  diberikan  adalah  sebagai  berikut  : (a). Pengenalan Hard Ware, (b). Pen genal an Card (lIO monitor),  (c). Pengenalan  Setup Bios, (d). Pemasangan   alat pendukung  (disk drive, hard disk), (e). Sistem  Operasi  (DOS, LAN), dan (f). Perawatanlpemeliharaan    komputer. Kata kunci  : P3HP, Inkubator  bisnis,  SMU Kalasan
Influence Of Drying Time And Temperature On Zirconium-Based Material (ZBM) Properties For 99Mo/99mTc Generator Development Munir, Miftakul; Sarmini, Endang; Herlina, Herlina; Pujiyanto, Anung; Saptiama, Indra; Kadarisman, Kadarisman; Kurnia, Shella
Jurnal Kimia dan Kemasan Vol. 40 No. 2 Oktober 2018
Publisher : Balai Besar Kimia dan Kemasan

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (558.172 KB) | DOI: 10.24817/jkk.v40i2.3772

Abstract

Zirconium-based material (ZBM) has an important role in producing Technetium-99m (99mTc) due to its high adsorption capacity to Molybdenum-99 (99Mo). The adsorption capacity of the ZBM depends on the specific surface area which is influenced by several parameters in the synthesis process. This study aims to investigate the influence of drying time and temperature on the structure and specific surface area of the ZBM. Synthesis of the ZBM was carried out using zirconium chloride, 2-propanol, water and tetrahydrofuran at 75 °C, 90 °C and 120 °C and for 3 hr, 5 hr and 7 hr, respectively. Functional group and specific surface area of the ZBM was analyzed by FTIR and BET method, respectively. At the variation of drying time, the functional group pattern showed by FTIR spectra was not significantly different. The O-H group of the ZBM increased as the drying temperature decreases. At 75 and 90°C, the specific surface area increased as the function of time was increased but was decreased at 120°C. The highest surface area of the synthesized ZBM had a poor performance as a 99Mo/99mTc generator material, whereas the eluate met the required standard.
UNJUK KERJA GENERATOR 99Mo/99mT DENGAN RADIOAKTIVITAS 99Mo 600 DAN 800 mCi BERBASIS PZC Kadarisman, Kadarisman; Gunawan, Adang Hardi; Lubis, Hotman; Herlina, Herlina; Sriyono, Sriyono; Abidin, Abidin
Jurnal Radioisotop dan Radiofarmaka Vol 12 (2009): JurnaL PRR 2009
Publisher : Jurnal Radioisotop dan Radiofarmaka

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ABSTRAK UNJUK KERJA GENERATOR 99Mo/99mTc DENGAN  RADIOAKTIVITAS 99Mo 600 DAN 800 mCi  BERBASIS  PZc. Radioisotop 99mTc mempunyai umur paro pendek (6 jam), pemancar sinar gamma mono-energik (140 KeV), mudah membentuk senyawa komplek dengan berbagai kit, dan tidak memancarkan partikel beta, maka 99mTcmerupakan radionuklida paling ideal untuk diagnosis dibidang kesehatan dibandingkan dengan radionuklida lainnya, sehingga diagnosis kedokteran nuklir menggunakan radionuklida ini lebih 80% dari diagnosis menggunakan radioisotop di seluruh dunia dan ada sekitar 9 juta prosedur untuk diagnosis. Beberapa jenis generator 99Mo/99mTc telah dikembangkan dan dikomersialkan, sistem ekstraksi menggunakan Metil Etil Keton (MEK), produk 99mTc terkontaminasi MEK, system kromatografi alumina, kapasitas serap alumina untuk 99Mo kecil, harus menggunakan 99Mo fisi, sistem gel Zr-Mo atau Ti-Mo tidak reprodusibel, yang terakhir adalah sistem Polymer Zirconium Compound (PZC). PZC berkapasitas serap tinggi untuk 99Mo,dapat menggunakan 99Mo hasil reaksi (n,y) yang lebih murah dan hasil radionuklida 99mTclebih terjangkau, teknologi tidak rumit dan proses relatif sederhana. Akhir-akhir ini, sistem generator 99mTc berbasis PZC telah dipelajari secara mendalam meliputi profit elusi 99mTc menggunakan salin, kapasitas serap PZC terhadap 99Mo, kemurnian radionuklioda 99mTcdan kestabilan PZC. Namun perkembangan pengembangan itu baru menggunakan tingkat radioaktivitas 99Mo relatif rendah (maksimum 272 mCi), sedangkan dalam generator 99mTcminimal harus berisi 300 mCi sid 1000 mCi 99Mo. Dalam penelitian ini telah dilakukan pembuatan kolom Mo-PZC dengan tingkat radioaktivitas tinggi (600dan 800 mCi) dengan menggunakan PZC sebanyak 5,86 dan 4,42 gram. Dalam eksperimen ini diperoleh radioaktivitas 99mTc243,86 dan 308,59 mCi dengan kemurnian radionuklida masing-masing sebesar 1,87 x 10-2 dan 1,32 x 10-2 ~Ci 99Mo/mCi 99mTc.Matriks 99Mo_PZC mempunyai ukuran patikel lebih kecil, yaitu berkisar antara 0,456 sid 0,583 I-lm.Kata kunci : Generator radioisotop 99Mo/99mTc,radioisotop 99Mo,PZC, lolosan 99Mo ABSTRACT PERFORMANCE OF 99Mo/99mTc GENERATORS WITH 600 AND 800 mCi RADIOACTIVITY OF 99Mo BASED ON PZC. Radioisotope of 99mTchas half life of 6 hours, emit mono-energic gamma ray (140 KeV), easily form complex compound with various kit, and does not emit beta particle. The 99mTc represents ideal radioisotope for diagnosis in health field compared to other radionuclides. More than 80% of the diagnosis in nuclear medicine uses the radionuclide and there is about 9 million procedures for diagnosis all over the world. Some types of generator of 99Mo/99mTchave been developed and commercially used. In the extraction system using Methyl Ethyl Keton (MEK), the produced 99mTcwas contaminated by MEK, while in chromatography using alumina, the absorbent capacity of alumina for 99Mo is small and can be used for 99Mo fission product only. Generators using gel of Zr-Mo or Ti-Mo are not reproducible. The generator system developed recently was generator using Polymer Zirconium Compound (PZC) as the adsorbent. PZC have high absorption capacities for 99Mo and can be used for 99Mo from (n,y) reaction. The cost of the generator is relatively low, the technology is not complicated and the process is relatively simple. Generator system of 99mTc based on PZC have been studied intensively including elution profile of 99mTcusing saline solution, absorbtion capacity of PZC for 99Mo, radionuclide impurities in 99mTcand stability of PZC. However, the radioactivity  of  99 Mo used is still relatively low (maximum 272 mCi), while in 99Mo/99mTcgenerator, the radioactivity of 99Mo is in the range of 300 mCi to 1000 mCi 99Mo. In this research, the experiment of generators with high radioactivity of 99Mo (6 mCi) was carried out. In this experiment, 99mTc with  radioactivity of 243.86 and 308.59 mCi was obtained. The Impurity of 99Mo break through were 1,87 x 10-2 and 1,32 x 10'2 f.!Ci 99Mo/mCi 99mTc.The matrix of 99I't10-PZChave small size, in the range of 0,456 to 0,583 f.!m.Key words : 99Mo/99mTc isotope generator, 99Mo isotope, PZC, 99Mo break through.00 – 800