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Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology)

jstni
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Published by Badan Tenaga Nuklir Nasional

ISSN : 14113481 EISSN : 25031287 DOI : https://search.crossref.org/?q=%22jurnal+sains+dan

Core Subject : Health, Science, Social, Engineering,

Biochemistry, Genetics & Molecular Biology Energy Environmental Science Materials Science & Nanotechnology Mechanical Engineering Medicine & Pharmacology Physics

Focus of Publication in Indonesian Journal of Nuclear Science and Technology : Result of experiment in the field of nuclear science and technology and its applications in various fields. Acceptable topics include: Radioisotope, Radiopharmacy, Nuclear Medicine, Nuclear Radiation and its Measurement, Nuclear Physics and Reactors, Nuclear Instrumentation and Radioactive Waste including its applications in the fields of health, biology, industry, agriculture, metallurgy and environment

Arjuna Subject : Kimia(semua kategori) - Kimia (Lain-Lain)

Articles 6 Documents

Search results for , issue "Vol 16, No 1 (2015): Februari 2015" : 6 Documents clear

Cover dan Redaksi, Vol 16, No:1, 2015 - Februari 2015 Muhamad Basit Febrian
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 16, No 1 (2015): Februari 2015
Publisher : BATAN

KARAKTERISASI FISIKO-KIMIA RADIOISOTOP 149Pm HASIL IRADIASI BAHAN SASARAN 148Nd ALAM Azmairit Aziz; Nana Suherman
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 16, No 1 (2015): Februari 2015
Publisher : BATAN

ABSTRAK KARAKTERISASI FISIKO-KIMIA RADIOISOTOP 149Pm HASIL IRADIASI BAHAN SASARAN 148Nd ALAM. Penyakit kanker merupakan salah satu masalah utama yang dihadapi Indonesia di bidang kesehatan. Radioisotop pemancar-β- dengan aktivitas jenis tinggi dapat digunakan untuk penandaan biomolekul sebagai radiofarmaka spesifik target untuk terapi sel kanker. Promesium-149 (149Pm) merupakan salah satu radiolantanida pemancar-β- yang me-miliki energi beta (Eβ-)maksimum sebesar 1,07 MeV (95,9 %) dan dapat dipertimbangkan untuk digunakan pada terapi kanker berdasarkan sifat nuklir yang dimilikinya. Radioisotop 149Pm dapat dibuat dengan cara tidak langsung melalui reaksi inti (n,γ) di reaktor nuklir menggunakan bahan sasaran isotop 148Nd (neodymium-148) dan radioisotop 149Pm yang dihasilkan adalah bebas pengemban (carrier free) sehingga memiliki aktivitas jenis tinggi. Pada penelitian ini digunakan bahan sasaran Nd2O3 alam yang diiradiasi selama ± 4 hari di Central Irradiation Position (CIP) RSG-G.A.Siwabessy – Serpong pada fluks neutron termal ~1014 n.cm-2.det-1. Radioisotop 149Pm dipisahkan dari bahan sasaran Nd2O3 hasil iradiasi menggunakan metode kromatografi ekstraksi. Larutan radioisotop 149PmCl3 yang dihasilkan dikarakterisasi secara fisiko-kimia meliputi penentuan kemurnian radiokimia menggunakan metode kromatografi kertas dan elektroforesis kertas. Kemurnian radionuklida ditentukan menggunakan spektro-meter-γ dengan detektor HP-Ge yang dilengkapi multichannel analyzer (MCA). Larutan 149PmCl3 yang diperoleh berupa larutan jernih, memiliki pH 2 dan konsentrasi radioaktif 4,2 – 7,4 mCi/mL. Larutan 149PmCl3 memiliki kemurnian radiokimia 99,70 ± 0,23% dan kemurnian radionuklida setelah pendinginan selama 9 hari sebesar 98,58 ± 0,44%. Larutan 149PmCl3 stabil selama 2 minggu pada temperatur kamar. Larutan radioisotop 149PmCl3 memiliki karakteristik fisiko-kimia yang memenuhi persyaratan untuk digunakan dalam pembuatan radiofarmaka ABSTRACT PHYSICO - CHEMICAL CHARACTERIZATION OF 149Pm RADIOISOTOPE FROM IRRADIATED NATURAL 148Nd TARGET. Cancer is one of the major problems encountered in the field of health in Indonesia. A beta-emitting radioisotope with high specific activity can be used for labeling of biomolecules as a targeted radiopharmaceutical for cancer therapy. Promethium-149 (149Pm) is one of beta-emitting radiolanthanides with beta energy (Eβ-) maximum of 1.07 MeV (95.9%) and can be considered to be used for cancer therapy based on its nuclear properties. Radioisotope of 149Pm can be produced by indirect methode through (n,γ) reaction in nuclear reactor using 148Nd (neodymium-148) target material and 149Pm was produced as a carrier free radioisotope, so that it has high specific activity. In this study, natural Nd2O3 target was irradiated for ± 4 days in central irradiation position (CIP) of RSG-G.A. Siwabessy – Serpong at a thermal neutron flux of ~ 1014 n.cm-2.sec-1. Radioisotope of 149Pm was separated from irradiated of Nd2O3 target using extraction chromatography method. The physico-chemical characterization of 149PmCl3 solution was studied involves the determination of its radiochemical purity using paper chromatography and paper electrophoresis methods. The radionuclide purity was determined using a γ-spectrometer with HP-Ge detector and coupled with a multichannel analyzer (MCA). 149PmCl3 was obtained as a clear solution, has a pH of 2 and radioactive concentration of 4.2 to 7.4 mCi/mL. 149PmCl3 solution has radiochemical purity of 99.70 ± 0.23% and radionuclide purity after cooling for 9 days of 98.58 ± 0.44%. 149PmCl3 solution was stable for 2 weeks at room temperature. 149PmCl3 solution has the physico-chemical characteristics that meet requirements for use in preparation of radiopharmaceuticals.

PREDIKSI KARAKTERISTIK TERMOFLUIDA PROSES PERPINDAHAN PANAS DI DALAM RUANG BAKAR INCINERATOR Veronica Indriati Sri Wardhani
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 16, No 1 (2015): Februari 2015
Publisher : BATAN

ABSTRAK PREDIKSI KARAKTERISTIK TERMOFLUIDA PROSES PERPINDAHAN PANAS DI DALAM RUANG BAKAR INCINERATOR. Penanganan limbah padat dengan proses pembakaran merupakan salah satu cara yang efektif sampai saat ini, instalasi incinerator masih menjadi perlatan pilihan yang dipergunakan untuk proses pembakaran. Namun penggunaan incinerator sebagai alat pembakaran sampah harus direncanakan dengan baik, karena efek yang dihasilkan adalah produk-produk destruktif yang justru bernilai negatif terhadap lingkungan. Mengingat proses pembakaran yang sangat kompleks di dalam incinerator, maka dilakukan simulasi dengan membuat suatu pemodelan menggunakan perangkat lunak compu-tational fluid dinamics (Fluent). Simulasi ini bertujuan untuk melihat karakteristik termo fluida yang terjadi di dalam ruang bakar incinerator meliputi variabel-variabel antara lain distribusi temperatur, sifat-sifat fisik fluida dan jenis aliran ( laminer atau turbulen ). Variabel-variabel tersebut akan mempengaruhi harga koefisien perpindahan panas konveksi (h). Perhitungan karakteristik termofluida yang meliputi panas yang mengalir (Q) dan koefisien perpindahan panas (h) pada tiga (3) titik pengukuran arah aksial diperoleh hasil koefisien perpindahan panas konveksi di ruang bagian dalam lebih besar 10 kali dari koefisien perpindahan panas konveksi di ruang bagian luar antara bata dalam dan bata luar. ABSTRACT THERMOFLUID characteristic prediction oF heat transfeR in the combustion chamber of incinerator. Handling of solid waste with the combustion process by installing the incinerator, is one effective way at present. However, the use of incinerators as a means of burning waste should be well planned, because of the resulted destructive products that have a negative impact to the environment. Considering the complexity process of combustion in the incinerator, the process simulation is done by using Computational fluid Dynamics software (Fluent). This simulation is proposed to obtain thermofluid characteristics such as variable temperature distribution, physical properties of the fluid and flow pattern (laminer or turbulent). These variables will affect the convection heat transfer coefficient (h). The Calculation characteristics of termofluida such as heat flow (Q) and coefficient heat transfer (h) on three (3) points in axial direction obtained the coefficient heat transfer convection inner space is greater 10 times than the coefficient heat transfer convection outer space between the inner brick and the outer brick.

VERIFIKASI PROGRAM PWR-FUEL DALAM MANAJEMEN BAHAN BAKAR PWR Surian Pinem; Tagor M. Sembiring; Mr Tukiran
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 16, No 1 (2015): Februari 2015
Publisher : BATAN

ABSTRAKVERIFIKASI PROGRAM PWR-FUEL DALAM MANAJEMEN BAHAN BAKAR PWR. Majemen bahan bakar dalam teras PWR tidak mudah karena jumlah perangkat bahan bakar dalam teras sebanyak 192 perangkat sehingga banyak kemungkinan penempatan bahan bakar dalam teras. Konfigurasi perangkat bahan bakar dalam teras harus tepat dan akurat sehingga reaktor beroperasi aman dan ekonomis. Untuk itu perlu dilakukan verifikasi program PWR-FUEL yang akan digunakan dalam manajemen bahan bakar PWR. Program PWR-FUEL didasarkan pada teori transport neutron dan diselesaikan dengan pendekatan metode difusi nodal banyak dimensi banyak kelompok dan metode difusi beda hingga (FDM). Tujuannya untuk memeriksa apakah program berfungsi dengan baik terutama untuk desain dan mana-jemen bahan bakar teras PWR. Verifikasi dilakukan dengan model pencarian teras setimbang pada tiga kondisi yaitu bebas boron, konsentrasi boron 1000 ppm dan konsentrasi boron kritis. Hasil perhitungan distribusi fraksi bakar rata-rata perangkat bahan bakar dan distribusi daya pada BOC dan EOC menunjukkan tren yang konsisten dimana perangkat bahan bakar dengan dengan daya yang tinggi pada BOC akan menghasilkan fraksi bakar yang tinggi pada EOC. Pada teras tanpa boron diperoleh faktor multiplikasi yang tinggi karena tidak adanya boron dalam teras dan efek produk fisi pada teras sekitar 3,8 %. Efek reaktivitas larutan boron 1000 ppm pada BOC dan EOC masing-masing 6,44 % dan 1,703 %. Distribusi fluks neutron dan kerapatan daya menggunakan metode NODAL dan FDM mempunyai hasil yang sama. Hasil verifikasi menunjukkan bahwa program PWR-FUEL berfungsi dengan baik terutama untuk desain dan pengolahaan bahan bakar dalam teras PWR. ABSTRACTTHE VERIFICATION OF PWR-FUEL CODE FOR PWR IN-CORE FUEL MANAGEMENT. In-core fuel management for PWR is not easy because of the number of fuel assemblies in the core as much as 192 assemblies so many possibilities for placement of the fuel in the core. Configuration of fuel assemblies in the core must be precise and accurate so that the reactor operates safely and economically. It is necessary for verification of PWR-FUEL code that will be used in-core fuel management for PWR. PWR-FUEL code based on neutron transport theory and solved with the approach of multi-dimensional nodal diffusion method many groups and diffusion finite difference method (FDM). The goal is to check whether the program works fine, especially for the design and in-core fuel management for PWR. Verification is done with equilibrium core search model at three conditions that boron free, 1000 ppm boron concentration and critical boron consentration. The result of the average burn up fuel assemblies distribution and power distribution at BOC and EOC showed a consistent trend where the fuel with high power at BOC will produce a high burn up in the EOC. On the core without boron is obtained a high multiplication factor because absence of boron in the core and the effect of fission products on the core around 3.8 %. Reactivity effect at 1000 ppm boron solution of BOC and EOC is 6.44% and 1.703 % respectively. Distribution neutron flux and power density using NODAL and FDM methods have the same result. The results show that the verification PWR-FUEL code work properly, especially for core design and in-core fuel management for PWR.

UJI PRAKLINIS 99mTc-KANAMISIN SEBAGAI RADIOFARMAKA UNTUK PENCITRAAN INFEKSI Iim Halimah; Ahmad Ridwan; Mukh Syaifudin
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 16, No 1 (2015): Februari 2015
Publisher : BATAN

ABSTRAK UJI PRAKLINIS 99mTc-KANAMISIN SEBAGAI RADIOFARMAKA UNTUK PENCITRA-AN INFEKSI. 99mTc-kanamisin merupakan salah satu radiofarmaka yang digunakan untuk mendiagnosis infeksi hingga ke bagian tubuh yang sangat dalam. Penelitian ini bertujuan untuk mendapatkan informasi mengenai karakteristik praklinis 99mTc-kanamisin meliputi toksisitas, sterilitas, pirogenitas, dan biodistribusi. Uji toksisitas dilakukan pada 5 ekor mencit yang diinjeksi 99mTc-kanamisin secara intra vena ekor, dilanjutkan dengan pengamatan sampai dengan 24 jam setelah injeksi. Hasil pengamatan menunjukkan bahwa 99mTc-kanamisin tidak bersifat toksik. Uji sterilitas dengan metode inokulasi 99mTc-kanamisin secara langsung pada medium nutrient agar dan tioglikolat cair menunjukkan bahwa 99mTc-kanamisin bersifat steril. Uji pirogenitas pada 3 ekor kelinci yang diinjeksi 99mTc-kanamisin secara intra vena pada telinga menunjukkan bahwa suhu total respon sebesar 2,9 oC, yang berarti 99mTc-kanamisin belum bebas pirogen. Biodistribusi 99mTc-kanamisin dilakukan pada mencit yang tidak diinfeksi dan yang diinfeksi dengan bakteri Escherichia coli dan Staphylococcus aureus secara intra-muskular pada 24 jam sebelum injeksi 99mTc-kanamisin. Beberapa sampel organ dan jaringan mencit diambil pada interval waktu 30, 60, dan 180 menit pasca injeksi 99mTc-kanamisin secara intravena melalui ekor mencit, menunjukkan bahwa 99mTc-kanamisin terakumulasi di dalam organ target yaitu otot paha kiri. Nilai rasio otot paha kiri terhadap otot paha kanan yang diperoleh sebesar 3,63 dan 5,64, masing-masing untuk E. coli dan S. aureus. Radiofarmaka 99mTc-kanamisin bersifat tidak toksik, steril, mengandung pirogen, terdistribusi di dalam tubuh mencit dengan baik, dan diekskresikan secara cepat dari dalam tubuh mencit melalui ginjal mulai 30 menit pasca injeksi, baik pada mencit yang diinfeksi bakteri maupun mencit yang tidak diinfeksi bakteri. ABSTRACT99mTc-KANAMYCIN PRECLINICAL TESTING AS A RADIOPHARMACEUTICAL FOR INFECTION IMAGING. Infectious disease is the leading cause of death in worldwide, especially in developing countries such as Indonesia. Early detection and determination of the exact location of infection by imaging methods can facilitate treatment. 99mTc-kanamycin is one of the radiopharmaceuticals that widely used for such purpose. The aim of the study was to obtain the information on the preclinical characteristics of 99mTc-kanamycin including toxicity, sterility, pirogenicity, and biodistribution. Toxicity test conducted in 5 mice injected radiopharmaceutical 99mTc-kanamycin intra venous tail, showed that the radiopharmaceutical was not toxic for 24 hours after intravenous injection. Sterility testing of radiopharmaceutical 99mTc-kanamycin conducted with direct inoculation on Nutrient Agar and liquid Thioglicolat medium showed that the radiopharmaceutical was sterile. Pyrogenicity test conducted in 3 rabbits injected with the radiopharmaceutical 99mTc-kanamycin showed that the total temperature response was 2.9oC, that means that the radiopharmaceutical was not free from pyrogen. Biodistribution of 99mTc-kanamycin at intervals of 30, 60, and 180 minutes post intravenously injection through the tail of mice, infected with Escherichia coli and Staphylococcus aureus intramuscularly 24 hours earlier, showed that 99mTc-kanamycin accumulates in the target organ of the left thigh muscle. The ratio values of left to right thigh muscle were 3.63 and 5.64 for E. coli and S. aureus, respectively. Radiopharmaceutical 99mTc-kanamycin was not toxic, sterile, pyrogen, distributed in the body of mice, and were rapidly excreted from the body through the kidneys starting 30 minutes post injection, both in bacterials infected or without bacterials infected mice. ABSTRACT 99mTc-KANAMYCIN PRECLINICAL TESTING AS A RADIOPHARMACEUTICAL FOR INFECTION IMAGING. Infectious disease is the leading cause of death in worldwide, especially in developing countries such as Indonesia. Early detection and determination of the exact location of infection by imaging methods can facilitate treatment. 99mTc-kanamycin is one of the radiopharmaceuticals that widely used for such purpose. The aim of the study was to obtain the information on the preclinical characteristics of 99mTc-kanamycin including toxicity, sterility, pirogenicity, and biodistribution. Toxicity test conducted in 5 mice injected radiopharmaceutical 99mTc-kanamycin intra venous tail, showed that the radiopharmaceutical was not toxic for 24 hours after intravenous injection. Sterility testing of radiopharmaceutical 99mTc-kanamycin conducted with direct inoculation on Nutrient Agar and liquid Thioglicolat medium showed that the radiopharmaceutical was sterile. Pyrogenicity test conducted in 3 rabbits injected with the radiopharmaceutical 99mTc-kanamycin showed that the total temperature response was 2.9oC, that means that the radiopharmaceutical was not free from pyrogen. Biodistribution of 99mTc-kanamycin at intervals of 30, 60, and 180 minutes post intravenously injection through the tail of mice, infected with Escherichia coli and Staphylococcus aureus intramuscularly 24 hours earlier, showed that 99mTc-kanamycin accumulates in the target organ of the left thigh muscle. The ratio values of left to right thigh muscle were 3.63 and 5.64 for E. coli and S. aureus, respectively. Radiopharmaceutical 99mTc-kanamycin was not toxic, sterile, pyrogen, distributed in the body of mice, and were rapidly excreted from the body through the kidneys starting 30 minutes post injection, both in bacterials infected or without bacterials infected mice.

KARAKTERISTIK PEMISAHAN RADIOLUTESIUM-177/177mLu DAN RADIOITERBIUM-169/175Yb PADA KOLOM RESIN LN-EICHROM Triani Widyaningrum; Mr Triyanto; Endang Sarmini; Umi Nur Sholikhah; Sunarhadijoso Soenarjo
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 16, No 1 (2015): Februari 2015
Publisher : BATAN

ABSTRAK KARAKTERISTIK PEMISAHAN RADIOLUTESIUM- 177/177mLu DAN RADIOITERBIUM-169/175Yb PADA KOLOM RESIN LN-EICHROM. Radiolutesium-177Lu keradioaktifan jenis tinggi merupakan salah satu radiolantanida yang banyak digunakan untuk menangani berbagai kasus kanker, namun di Indonesia penggunaan radiofarmaka bertanda 177Lu belum dapat dijanjikan karena teknik produksi radioisotop primernya belum dikuasai. Prospek produksi 177Lu melalui reaksi inti 176Yb (n,g) 177Yb* à 177Lu* + β– dipelajari melalui metode pemisahan matrik 177/177mLu-169/175Yb/176Yb dalam sistem kromatografi kolom resin LN-Eichrom. Profil fraksinasi dan karakteristik pemisahan dipelajari dengan pemeriksaan keradioaktifan dan analisis spektro-metri-g terhadap hasil elusi larutan sasaran pasca iradiasi. Bahan sasaran digunakan 176Yb2O3 alam dan 176Lu2O3 diperkaya. Hasil penelitian menunjukkan bahwa radiolutesium-177/177mLu dapat dipisahkan dari matrik radioiterbium-169/175Yb/natYb melalui sistem kromatografi kolom dengan fase diam resin LN-Eichrom dan fase gerak larutan HNO3, dengan konsentrasi antara 1,5 – 4 M untuk mendapatkan pemisahan yang efektif, selektif dan kuantitatif. Reaksi inti 176Yb(n,g) 177Yb* à 177Lu + β– merupakan model reaksi inti yang perlu dipertimbangkan walau-pun harus melibatkan tahapan pemisahan produk 177Lu dari matrik sasaran Yb pasca iradiasi. Prosedur pemisahan yang dilakukan masih perlu diperbaiki melalui pemilihan jenis dan konsentrasi fase gerak pengelusi yang lebih tepat. ABSTRACT SEPARATION CHARACTERISTIC OF RADIOLUTETIUM-177/177mLu AND RADIOY-TTERBIUM-169/175Yb ON LN-EICHROM RESIN COLUMN. High specific activity radiolutetium-177Lu is one of radiolanthanides that is widely used to handle variety of cancer cases, but in Indonesia the use of 177Lu-labeled-radiopharmaceutical can not be promised yet as the primary radioisotope production techniques have not been mastered. The prospect of 177Lu production based on the nuclear reaction of 176Yb (n,g) 177Yb * ® 177Lu * + β– in the BATAN’s G.A. Siwabessy reactor was learned through the separation characteristics of 177/177mLu-169/175Yb /176Yb process matrices in the LN-Eichrom resin column chromatography. The separation and fractionation profiles were characterized by radioactivity measurement as well as g-spectrometric analysis of the eluting post-irradiated target solution. The target materials used were natural 176Yb2O3 and enriched 176Lu2O3. The results showed that radiolutetium-177/177mLu can be separated from the radioiterbium-169/175Yb/natYb matrix by column chromatography system with a stationary phase of LN-Eichrom resin using HNO3 solution as the mobile phase, but the concentration of HNO3 used is a critical variable, between 1.5 - 4 M, to obtain an effective separation selectively and quantitatively. The nuclear reaction of 176Yb (n,g) 177Yb* ® 177Lu + β– using natural Yb2O3 is considered to be better, although it must involve 177Lu product separation stage from the post-irradiated natural Yb target matrix. The presented separation procedure still needs to be improved through the selection of the type and the concentration of the mobile phase used to gain more appropriate elution solvent.

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