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All Journal Jurnal Radioisotop dan Radiofarmaka Jurnal Kimia dan Kemasan Makara Journal of Technology Jurnal Kefarmasian Indonesia
Rohadi Awaludin
Pusat Teknologi Radioisotop dan Radiofarmaka Gd. 11 Puspiptek, Serpong, 15314
Chemical Engineering, Chemistry & Bioengineering Chemistry Civil Engineering, Building, Construction & Architecture Electrical & Electronics Engineering Engineering Materials Science & Nanotechnology Mechanical Engineering Medicine & Pharmacology

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RADIOAKTIVITAS JENIS DAN KEMURNIAN RADIONUKLIDA LUTESIUM-177 DIPRODUKSI MENGGUNAKAN REAKTOR G.A. SIWABESSV Awaludin, Rohadi
Jurnal Radioisotop dan Radiofarmaka Vol 18, No 1 (2015): JURNAL PTRR 2015
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

Lutesiurn-177 banyak dirnanfaatkan dalam pengembangan radiofarmaka yang didasarkan pada karakteristik radionuklida tersebut. Pada proses pembuatan Lu-I77, radioaktivitas jenis dan kemurnian radinuklida yang diperoleh dipengaruhi oleh kelimpahan Lu-176, fluks netron dan lama iradiasi. Pada studi ini dilakukan perhitungan radioaktivitas Lu-l77 dan radionuklida pengotor Lu-l77m dari pada kondisi iradiasi di Reaktor G.A. Siwabessy. Pada perhitungan ini, iradiasi dilakukan di pneumatic rabbit system (PRS) dengan fluks netron 5xlO13 n.s·1.cm·2 dan di central irradiation position (CIP) dengan fluks netron 1,3x1014 n.s'lcm' 2. Hasil perhitungan menunjukkan bahwa iradiasi di PRS tidak dapat mencapai nilai radioaktivitas jenis minimum yang diharapkan yaitu sebesar 20,0 GBq/mg jika menggunakan lutesium alam. Jikamenggunakan target diperkaya 90%, radioaktivitas jenis minimum terse but dapat dicapai denganiradiasi selama 15 jam. Untuk iradiasi di CIP, radioaktivitas jenis minimum tersebut dapat dicapai dengan iradiasi selama 3 jam dengan menggunakan target diperkaya 90% dan selama 17 hari jika menggunakan lutesium alam. Kandungan radionuklida pengotor Lu-l77m kurang dari 0,1% sampai dengan iradiasi selama 12 hari pada saat akhir iradiasi. Kandungan Lu-177m meningkat dengan cepat setelah iradiasi dihentikan dan mencapai 0,1% setelah peluruhan selama 24 hari. Lutetium-l77 is widely used in the development of therapeutic radiopharmaceutical. It is based on the characteristics of the radionuclide. In the Lu-l77 production, the specific radioactivity and radionuclide purity is affected by the abundance of Lu-176 in target material, neutron flux and length of irradiation time. In this study, calculations of Lu-l77 specific radioactivity and Lu-l77m radionuclide impurities were carried out. In this calculation, neutron flux of 5xl013 n.s·1cm·2 in PRSand and 1,3xI014 n.s·1cm-2 in ClP were used. Calculation results showed that the irradiation of natural lutetium in the PRSresulted in Lu-l77 with specific radioactivity less than of the minimum specific radioactivity of 20.0 GBq/mg. The minimum radioactivity can be obtained by using enriched lutetium (enrichment 90%) for 15 hours of irradiation. Irradiation in ClP resulted in Lu-177 with specific radioactivity higher than 20.0 GBq/mg by 3 hours of irradiation using enriched target and 17 days of irradiation using natural lutetium. Radionuclide impurity of Lu-l77m was less than 0.1% for 12 days of irradiation. However, the percentage of Lu-l77m increased rapidlyafter irradiation and reached 0,1% after 24 days of decay. 
PERHITUNGAN PEMBUATAN KADMIUM-I09 UNTUK SUMBER RADIASI XRF MENGGUNAKAN TARGET KADMIUM DIPERKAYA DI REAKTOR G.A. SIWABESSY Awaludin, Rohadi
Jurnal Radioisotop dan Radiofarmaka Vol 14, No 1 (2011): Jurnal PRR 2011
Publisher : Jurnal Radioisotop dan Radiofarmaka

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ABSTRAKPERHITUNGAN PEMBUATAN KADMIUM-I09 UNTUK SUMBER RADIASI XRFMENGGUNAKAN TARGET KADMIUM DIPERKAYA DI REAKTOR G.A. SIWABESSY.Radioisotop kadmium-l09  merupakan  salah  satu  sumber  radiasi  yang  digunakan pada  X-ray  fluorescence (XRF)  dengan  radioaktivitas bervariasi antara 3,7 MBq - 37 GBq. Perhitungan pembuatan sumber radiasi kadmium-l09 untuk XRF melalui aktivasi neutron telah dilakukan menggunakan sasaran kadmium diperkaya di Central Irradia tion  Position (CIP)  reaktor  G.A. Siwabessy.  Pada  perhitungan  ini digunakan target kadmium diperkaya   dengan  pengayaan  Cd-l08   sebesar  70%,  berbentuk silinder dengan   diameter  2,8 mm  dan  panjang  2,8 mm. Hasil  perhitungan  menunjukkan bahwa  I09Cd dengan radioaktivitas 1,378 GBq  dapat  dihasilkan pada  saat end   of irradiation (EOI) dengan waktu iradiasi  selama  12 hari. Radioisotop  lain  yang  turut dihasilkan dalam iradiasi ini berupa I07Cd, 115mCd,115Cd,117mCddan 117C dengan radioaktivitas saat EOI masing-masing  sebesar  377 MBq, 53,0 MBq,  2535  MBq, 113 MBq dan 56,5 MBq. Setelah satu  bulan, r adioisotop  pengotor  yang  masih  menyisa adalah  115  mCd.  Untuk   mendapatkan  radioaktivitas  I09Cd   dengan   kemumian radionuklida   99,0 %   diperlukan   waktu   peluruhan   selama   3,2  bulan.  Radioaktivitas  I09Cd meluruh  menjadi  1,193  GBq  setelah  peluruhan selama waktu tersebut.Kata kunci: kadmium-109, XRF, aktivasi neutron.Cadmium109 is used as a radiation source in the X-ray fluorescence (XRF) with radio-activity varies  3.7 MBq - 37 GBq. Calculation for production of   the source by neutron activation at G.A. Siwabessy Reactor using enriched cadmium has been carried out. An enriched cadmium cylinder with diameter 2.8 mm and length 2.8 mm was used in the calculation. Calculation  results  showed  that '09Cd  with  radioactivity  1.378 GBq was obtained at the end of irradiation (EOI)  for 12 days  of  irradiation. Radioisotopes  of '07 Cd,  "5m Cd, "5 Cd, "7m Cd  and  117 Cd  were  produced  in  the  iradiation  with radioactivity 377 MBq, 53.0 MBq, 2535 MBq, 113 MBq and 56.5 MBq respectively. After a month, radioisotope of "5mCd still remained in the irradiated cadmium. For  obtain- ing radionuclide purity of I09Cd higher than 99.0%, the irradiated cadmium should be decayed  for  3.2 months. Radioactivity  of  I09Cdwas 1.193 GBq after 3.2 months  of decay.Key words: cadmium-l 09, XRF, neutron activation.
PRODUKSI TEMBAGA-64 MENGGUNAKAN SASARAN TEMBAGA FTALOSIANIN Awaludin, Rohadi; Abidin, Abidin; Sriyono, Sriyono; Herlina, Herlina
Jurnal Radioisotop dan Radiofarmaka Vol 9 (2006): jurnal PRR 2006
Publisher : Jurnal Radioisotop dan Radiofarmaka

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PRODUKSI TEMBAGA-64 MENGGUNAKAN SASARAN TEMBAGA FTALOSIANIN. Radioisotop tembaga-64 (64Cu) merupakan pemancar positron yang memiliki beberapa kegunaan. Radioisotop ini dapat diproduksi dari 63 Cu melalui aktivasi neutron. Untuk mendapatkan radioisotop dengan radioaktivitas jenis yang tinggi, radioisotop ini dapat diproduksi memanfaatkan reaksi Szilard Chalmer, yaitu memanfaatkan lepasnya 64 Cu hasil iradiasi dari matrik sasaran. Tujuan dari penelitian ini adalah mendapatkan karakteristik 64Cu yang dapat diproduksi menggunakan reaktor G.A. Siwabessy dari sasaran tembaga ftalosianin. Tembaga ftalosianin sebanyak 200 mg diiradiasi di posisi pneumatic rabbit system selama 30 menit. Hasil iradiasi diukur menggunakan gamma ionization chamber untuk mendapatkan radioaktivitas yang dihasilkan. Kemurnian radionuklida diukur menggunakan spektrometer gamma. Dari tiga kali iradiasi diperoleh 64 Cu dengan radioaktivitas sebesar 5,29; 5,70 dan 5,65 mCi. Dari pengukuran menggunakan spektrometer gamma diketahui bahwa tidak ada radionuklida lain yang terdeteksi. Dari pemisahan menggunakan metode emulsi masih diperoleh yield yang rendah sebesar 2,59; 3,18 dan 5,33%. Kata kunci: tembaga-64, produksi radioisotop, tembaga ftalosianin PRODUCTION OF COPPER-64 USING COPPER PHTHALOCYANINE TARGET. Copper-64 is a positron emmiter radioisotope with a wide range of applications. The radioisotope can be produced by neutron activation method from 63 Cu. For obtaining high specific radioactivity, Szilard Chalmer method can be applicated, using the recoiling of 64 Cu from the target matrix. The objective of this study is obtaining the characteristics of 64 Cu that is produced using G.A. Siwabessy reactor with copper phthalocyanine target. Copper phthalocyanine 200 mg was irradiated at pneumatic rabbit sytem of GA Siwabessy reactor for 30 minutes. The radioactivity of Cu was measured by gamma ionization chamber. The radionuclide purity was determined by gamma spectrometer. From 3 times of irradiation of 200 mg of copper phthalocyanine, the Cu as high as 5.29, 5,70 and 5,65 mCi was obtained. The results of gamma spectrometer measurement showed that any other radioisotopes were not detected. Low yield (2.59; 3.18 and 5.33%) was obtained by separation using emulsion method. Key words: Copper-64, radioisotope production, copper phthalocyanine.
PERHITUNGAN PEMBUATAN EMAS-192, IRIDIUM-192 DAN LUTESIUM-177 DENGAN AKTIVASI NEUTRON UNTUK PARTIKEL NANO RADIOAKTIF Awaludin, Rohadi
Jurnal Radioisotop dan Radiofarmaka Vol 11 (2008): Jurnal PRR 2008
Publisher : Jurnal Radioisotop dan Radiofarmaka

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CALCULATION OF PRODUCTION OF GOLD-198, IRRIDIUM-192 ANDLUTETIUM-177 BY NEUTRON ACTIVATION FOR RADIOACTIVE NANOPARTICLE. It was reported that nanoparticle was effective for cancer treatment by thermotherapy. It is also possible to kill cancer cell by radiation of radioisotope from nanoparticle. A study on production ofradioactive nanoparticles by neutron activation has been carried out. Nanoparticles of gold, iridium and lutetium with diameter of 100 nm were studied. Calculations were carried out for irradiation at central irradiation position (CIP) of GA siwabessy reactor for 12 days. Calculation results showed that gold-198 with radioactivity of 0.378 Bq was produced in the gold nanoparticle. In the irridium nanoparticle, 192Irwith radioactivity of 0.179 Bq was produced. Radioisotope of 194Irwas also produced with radioactivity 0.337Bq at the end of irradiation in the iridium nanoparticle. The radioisotop decayed fast and became 0.000133Bq after 10 days. In the lutetium nanoparticle, I77Lu with radioactivity of 0.0884Bq was produced. In the lutetium nanoparticle, 176mLuand 177mLuwerealso produced. Lutetium-176m decayed fast and I77Lu radioactivity was 0.0095% of the I77Lu radioactivity at the end of irradiation. During neutron irradiation, the nanoparticle was put in the quartz ampule and aluminum capsules. Radioisotopes with short half life were produced in thequartz and aluminum.Keywords: gold-198, iridium-l92, lutetium-l77, neutron activation27
Neutron Irradiation on SS316 Material for Radioactive Endovascular Stent Production Awaludin, Rohadi; Abidin, Abidin; Sriyono, Sriyono
Makara Journal of Technology Vol. 12, No. 2
Publisher : UI Scholars Hub

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Neutron Irradiation on SS316 Material for Radioactive Endovascular Stent Production. It was reported that restenosis could be prevented by radioactive endovascular stent. SS316 material of endovascular stent has been irradiated at pneumatic rabbit system of G.A. Siwabessy reactor for 5 minutes for producing radioactive stent by neutron activation. After 10 days of decay, the irradiated SS316 was measured by gamma spectrometer. The radioisotopes of 51Cr, 59Fe and 60Co were detected in the irradiated SS316 with radioactivity of 5990, 107 and 109 Bq/mg respectively. The Calculation results showed that radioisotopes of 51Cr, 59Fe and 55Fe were produced by neutron activation. The radioactivity of 51Cr, 59Fe and 55Fe were 6051, 70 and 110 Bq/mg respectively. In the irradiated materials, the 55Fe was not detected because the radioisotope emitted radiation with very low energy (5.9 keV). It is considered that radioisotope of 60Co was produced from cobalt impurity in the SS316.
Preparation of Radioactive Gold Nanoparticle by Neutron Activation Awaludin, Rohadi
Makara Journal of Technology Vol. 13, No. 1
Publisher : UI Scholars Hub

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Preparation of Radioactive Gold Nanoparticle by Neutron Activation. It was reported that gold nanoparticle could be used for cancer therapy using thermal effect. It is possible to kill cancer cells using radiation of radioisotope. Study on preparation of radioactive gold by neutron activation at central irradiation position (CIP) of G.A. Siwabessy reactor with neutron flux 1.26 x 1014 neutron s-1cm-2 has been carried out. It was revealed that a radioisotop of gold (198Au) was produced by neutron activation from natural gold. Calculation results showed that 198Au with radioactivity of 0.366 Bq, 2.93 Bq, 9.90 Bq and 23.4 Bq was produced for nanoparticle with diameter of 100, 200, 300 and 400 nm by neutron irradiation for 12 days. The saturation factor was 96.5%. After 10 days of decay, the radioactivity was 0.027 Bq, 0.223 Bq, 0.753 Bq and 1.78 Bq in nanoparticle with diameter of 100, 200, 300 and 400 nm. The radionuclide impurities were 108Ag, 110mAg, 64Cu, 66Cu, 205Pb and 209Pb with the total radioactivity was 4.31 x 10-5 % of the total radioactivity of 198Au at the end of irradiation.
Preparasi Radiofarmaka Nanokoloid Human Serum Albumin (HSA) untuk Limfosintigrafi Yunilda, Yunilda; Awaludin, Rohadi
Jurnal Kefarmasian Indonesia VOLUME 7, NOMOR 1, FEBRUARI 2017
Publisher : Pusat Penelitian dan Pengembangan Biomedis dan Teknologi Dasar Kesehatan

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22435/jki.v7i1.3479

Abstract

Nanocolloid human serum albumin (HSA) labeled with technetium-99m is widely used in nuclear medicine for detection of breast cancer through examination of sentinel lymph node (SLN). SLN examination is used to detect the spread of cancer cells before and after surgery. Accumulation of a radiopharmaceutical in lymph nodes was detected by using a gamma cameraor SPECT. The aim of this study is to establish the protocol of HSA nanocolloid preparation with composition and specification in accordance with the Technical Leaflet Nanocoll Albumon which refers to The Society of Nuclear Medicine and Molecular Imaging (SNMMI) and European Association of Nuclear Medicine (EANM).This study includes the step of preparation and quality test. The method was carried out by means of protein denaturation of HAS at certain pH and heating at certain temperature. Quality tests were carried out using particle size analyzer (PSA) to determine the particle size, Transmission Electron Microscopy (TEM) to observe the morphology of the particles, and paper chromatography to measure radiolabeling yield. This study has obtained the particle size 80% of 95% and pH of 7.3–7.4. The result was a protocol of preparing HSA nanocolloid.
Co-Authors . Sulaeman A.A. Ketut Agung Cahyawan W Abdul Mutalib Abdul Muthalib Abidin Abidin Adang Hardi Gunawan Anung Pujianto Anung Pujiyanto, Daya Agung Sarwono Diandono Kuntjoro Yoga Endang Sarmini Herlina Herlina Hotman Lubis Ibon Suparman Indra Saptiama Karyadi Karyadi Mochamad Subechi, Sriyono Sriyono Sulaiman Sulaiman Triani Widyaningrum Yunilda Yunilda