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INDONESIA
Jurnal Radioisotop dan Radiofarmaka
Published by Badan Tenaga Nuklir Nasional
ISSN : -     EISSN : -     DOI : -
Core Subject : Health,
Medicine & Pharmacology
Jurnal Radioisotop dan Radiofarmaka (Journal of Radioisotopes and Radiopharmaceuticals) bertujuan untuk memajukan ilmu pengetahuan dan teknologi di bidang radioisotop, radiofarmaka dan bidang terkait, yang diwujudkan dalam bentuk makalah ilmiah hasil penelitian atau tinjauan dan gagasan.
Arjuna Subject : -
Articles 5 Documents
 1 
Search results for , issue "Vol 11 (2008): Jurnal PRR 2008" : 5 Documents clear
ANALISIS PENGAKTIVAN NEUTRON Soenarjo,, Sunarhadijoso
Jurnal Radioisotop dan Radiofarmaka Vol 11 (2008): Jurnal PRR 2008
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

NEUTRON ACT IVATION ANALYSIS. Neutron Activation Analysis (NAA) is anelement analysis based on radioactivity characters induced by thermal neutron irradiation on target nucleus. This technique is one of the utilizations of nuclear technique in the field of chemical analysis. As compared to the non-nuclear technique based analytical method, the NAA can be superior although it can only be performed in certain analytical chemistry laboratory due to the requirement and regulation on radiation protection. The presented paper is to give brief introduction on basic principle, grouping, methodology as well as data interpretation and calculation of the NAA method. Some important aspects in connection with implementation of NAA are also discussed. In general, this paper is expected to give positive insight and understanding on the application ofnuclear techniques in the daily life, especially concerning to principle, procedure and data interpretation of NAA.keywords: Neutron activation analysis, application of nuclear techniques, radioactivity, yspectrometry,Kayzero method.
ANALISIS PEMBENTUKAN PENGOTOR RADIONUKLIDA PADA UJI PRODUKSI IODIUM-125 Awaludin, Rohadi; Lubis, Hotman; Pujianto, Anung; Sarwono, Daya Agung; Suparman, Ibon
Jurnal Radioisotop dan Radiofarmaka Vol 11 (2008): Jurnal PRR 2008
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Abstract

ANALISIS PEMBENTUKAN PENGOTOR RADIONUKLIDA PADA UJI PRODUKSI IODIUM-125. Telah dilakukan evaluasi pembentukan radionuklida pada uji produksi Iodium-125 (125I) menggunakan target xenon diperkaya. Dari uji produksi yang telah dilakukan 9 kali diperoleh bahwa sampai dengan uji produksi ke-6 tidak ditemukan adanya pengotor radionuklida. Namun pada uji produksi ke 7, 8 dan 9 ditemukan adanya Iodium-126 (126I) dengan persentase 0,088%, 0,20% dan 0,28%. Radioisotop 126I dihasilkan dari penangkapan neutron oleh 125I yang telah terbentuk di dalam kamar iradiasi. Radioisotop ini ikut terbawa ke dalam botol peluruhan bersama sama dengan gas xenon hasil iradiasi pada saat pemindahan ke botol peluruhan. Diduga bahwa filter penyaring iodium yang telah dipasang di dalam fasilitas produksi 125I telah berkurang kinerjanya. Pengotor radionuklida lain yang memungkinkan terbentuk adalah 137Cs dari isotop 136Xe yang terkandung di dalam target xenon. Sampai dengan uji produksi ke-9 tidak ditemukan adanya pengotor 137Cs di dalam hasil uji produksi. Diduga bahwa 137Cs yang terbentuk tetap tertahan di kamar iradiasi. Kata kunci: Iodium-125, produksi radioisotop, pengotor radionuklida. ANALYSIS OF RADIONUCLIDE IMPURITY FORMATION IN IODINE-125 PRODUCTION TEST. Evaluation on formation of radionuclide impurity in iodine-125 (125I)production tests has been carried out. The production tests have been carried out 9 times and the radionuclide impurity was not found until the 6th test. However, The radionuclide impurity I was found in the 7th, 8th and 9th test with percentage of 0.088, 0.20 and 0.28%. Iodine-126 was produced by neutron capture of 125I in the irradiation chamber. The radioisotope moved to the decay pot together with the irradiated xenon gas. It is considered that the performance of the iodine filter has decreased. Other possibly produced radionuclide impurity is not detected in the product. It is considered that the produced chamber. Keywords: Iodine-125, radioisotope production, radionuclide impurity.
PRODUCTION OF IMMUNORADIOMETRICASSA Y (IRMA) CA 15.3 KIT COMPONENT FOR DETECTION OF BREAST CANCER Widayati, Puji; Ariyanto, Agus; Sutari, Sutari; Mondrida, Gina; Darwati, Siti
Jurnal Radioisotop dan Radiofarmaka Vol 11 (2008): Jurnal PRR 2008
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Abstract

PRODUCTION OF IMMUNORADIOMETRICASSA Y (IRMA) CA 15.3 KITCOMPONENT FOR DETECTION OF BREAST CANCER. YKI has ranked that breast cancer as a second deseas in causing death of Indonesian women (, 2007). This phenomenon has been caused by the low level of public awareness in early detection of cancers. As a consequences this kind of cancer has generally been diagnosed in advanced stadium which is difficult to be treated  In spite of this, the disease actually can be detected early by measuring level of CA 15.3, a tumor marker for breast cancer. One of such in vitro method is immunoradiometricassay (IRMA) for CA 15.3. The CA 15.3 itself is a glycoprotein of heterogen compound capable of reacting with monoclonal antibody CA 15.3. Production of the IRMA CA 15.3 kit has been performed in the Center for Radioisotope and Radiopharmac.eutical, National Nuclear Energy Agency of Indonesia. Optimization of the kit component has been carried out using several parameter including type ofmonoclonal antibody for tracer and buffer coating type. The results showed that monoclonal anti CA M37901M type is better than M37552M type for tracer production. The M3790lM gave yield about 79.51%, with specific activity 29.12 ~Ci/~g, radiochemical purity 94.21% and %B/T about11.94%. Several buffers have been evaluated and 0.05 M pH 9.6 carbonate bicarbonate buffer showed the highest specific binding when it was used as coating buffer. Preparation of IRMA CA 15.3 standard solution gave a linier relation between CA 15.3 concentration and the maximumbinding (%B/T) Y=0.227X+0.5177 and correlation coefficient R 0.9840Keywords: Radioimmunoassay, Immunoradiometricassay, tumor marker, CA-15.3
PREPARASI DAN STUDI AWAL BIODISTRIBUSI 99mTc -IMUNOGLOBULIN M YANG AKAN DIGUNAKAN SEBAGAI PREPARAT PENATAH INFEKSI/INFLAMASI A, Laksmi; Setiowati, Sri; Karyadi, Karyadi; Mondrida, Gina; W, Widyastuti; A., Agus
Jurnal Radioisotop dan Radiofarmaka Vol 11 (2008): Jurnal PRR 2008
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Abstract

PREPARATION AND BIODISTRIBUTION STUDY OF 99mTc . IMMUNOGLOBULIN M AS INFECTION/INFLAMMA TION IMAGING AGENT. Thesuperiority of radiopharmaceutical compare to the other techniques of medical services, especially for diagnosis and therapy of several deadly diseases such as cancer or diagnosis of infection and iflammmation . Infection diseases are common in Indonesia, Nuclear medicine techniques which uses polyclonal antibody based radiopharmaceutical labeled with technetium-99m offers an alternative method of diagnosis infection/inflammation. Preparation of 99mTc- ImmunoglobulinM(99mTc_IgM) and its analysis have been carried out. This preparation needs several steps, first reducing IgM using mercaptoetanol with molar ratio 1:2000-12000, purification using PO-IO column ( sephadex G-25,Pharmacia), and the reduced IgM was labeled with 99mTcand MDP astranschelator. The reduced IgM was analysed using size exlusion_HPLC The radiochemical purity of 99mTc_IgM was analysed using TLC/paper chromatography. The stability in the human body was carried out by using fresh human serum after 1 and 2 hours incubation, Biodistribution test oninfected mice was carried out, the radiochemical purity of 99mTc_IgM analysed with TLC/paper chromatography was higher than 90 % for molar ratio Ab:Me 1:12000. The stability of labeled IgM in fresh human serum was stable after 1 and 2 hours incubation, biodistribution test showed higher uptake in the site of infection ( right thigh) compare to the site of uninfection ( left thigh).Keywords: Antibody, immunoglobulin-M, biodistribution,99mTc, infection/inflammation19
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
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Abstract

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

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