Badan Tenaga Nuklir Nasional: Jurnal BATAN
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Simulasi Perilaku Fluks Neutron di Reaktor RSG-GAS dengan Metode RUNGE KUTTA
Full text linkPemodelan reaktor sebagai sebuah titik menghasilkan satu set pasangan persamaan diferensial biasa yang disebut sebagai persamaan kinetika reaktor titik (reactor point kinetic). Persamaan tersebut merupakan persamaan simultan orde satu yang menggambarkan perilaku reaktor gayut waktu. Persamaan kinetika reaktor titik dapat diselesaikan secara numerik, salah satunya dengan metode Runge Kutta Orde 4. Metode Runge Kutta Orde 4 dipilih karena memberikan hasil perhitungan yang lebih akurat meskipun dengan pemrograman yang relatif lebih sulit. Pemrograman dilakukan dalam bahasa FORTRAN, sedangkan hasil perhitungan divisualisasikan dengan Matlab. Penelitian ini bertujuan menyajikan penyelesaian persamaan kinetika reaktor titik secara numerik menggunakan metode Runge Kutta Orde 4 untuk menggambarkan hubungan reaktivitas dengan fluks neutron dalam teras reaktor. Langkah pertama, penentuan nilai densitas neutron awal (No), konsentrasi prekursor neutron awal (Co), reaktivitas awal (ρo), fraksi neutron kasip (βi), waktu generasi neutron kasip, dan konstanta peluruhan prekursor (λi). Langkah kedua, menyelesaikan persamaan diferensial densitas neutron dan konsentrasi prekursor dengan metode Runge Kutta Orde 4, Langkah ketiga, melakukan simulasi insersi reaktivitas step, sinusoidal dan reaktivitas fungsi densitas neutron. Langkah keempat, membuat visualisasi dengan Matlab. Data yang digunakan dalam perhitungan kinetika reaktor titik adalah data parameter kinetika teras TWC Silisida RSG-GAS Tabel V-17 LAK Rev. 11 tahun 2020. Hasil kajian menunjukkan bahwa penyelesaian persamaan kinetika reaktor titik dengan metode Runge Kutta Orde 4 menunjukkan perilaku fluks neutron di dalam teras akibat insersi reaktivitas yang sesuai dengan teori kinetika reaktor. Hasil kajian juga dapat menggambarkan hubungan antara reaktivitas dengan fluks neutron dalam teras pada insersi reaktivitas undak (step), sinusoidal, dan reaktivitas fungsi densitas neutro
OPPORTUNITY TO PRODUCE RADIOISOTOPES ASTATINE-211 USING DECY-13 CONCEPTUAL DESIGN WITH COMPUTATIONAL APPROACH
No full textTo catch up research gap with developed countries, Indonesia would build a cyclotron type accelerator that has the code name DECY-13. Detailed design and conceptual design of DECY-13 were published, thus to accelerated applied research of DECY-13, it is necessary to hold a preliminary study even before the cyclotron is commissioned. Astatine-211 (211At) is an alpha-rays emit radioisotope that is easy to direct labeling for targeted alpha therapy. Targeted alpha therapy (TAT) is the selectively deliver therapy that uses alpha-ray base radioisotopes that are produced using a cyclotron like DECY-13. DECY-13 was designed to accelerate a proton to 13 MeV. however, it does not rule out the possibility of accelerating alpha particles. A computational approach will be used to simulate the possibility of DECT-13 to accelerate alpha particles for the production of 211At from natural Bismuth. The theoretical calculation was predicting that the alpha particle (helium nucleus) could be accelerated in DECY-13, but the energy decreased increasingly after hitting niobium layer twice and helium cooling layer into 4.06 MeV. The 0.924 grams of natural bismuth was irradiated 8 hours long and 4 hours cooling. At EOB was not found radioisotopes, radioactivity and dose emitted. The inability to produce 211At because the energy of the accelerated alpha particles has not been able to penetrate the bismuth nucleus. the continuation simulation successfully predicts if the niobium layer thinned to 125 mm can be obtained 211At with low impurity. on the other side, if the energy of DECY-13 would be increased until 28 MeV 211At can be produced but the impurity was increased to. Furthermore, DECY-13 Cyclotron is not able to produce 211At from bismuth-209. To obtain 211At from 209Bi, it is necessary to create another engineering design of cyclotron or use another proton-base reaction
DESIGN OF SODIUM IODINE BASED SURVEYMETER WITH ATMEGA328P MICROCONTROLLER
No full textSurvey meter is a device for radiation exposure and dose rate measurements which is mainly used in radiation protection. The main purpose of this work is to present testing results of a designed surveymeter by comparing with a calibrated Peranuk surveymeter. The designed surveymeter consists of a NaI(Tl) scintillation detector as gamma radiation sensor with an ATMega328P processor as signal processing system and a 3.5-inch LCD as a data display. From the testing results, a count rate (cps) to dose rate (Sv/h) conversion factor of 0.0254 was obtained with dose rate reading deviations range from 0.03% to 6.26%
ESTIMASI PANAS GAMMA PADA PRODUKSI RADIOISOTOP Lu-177, Ir-192, DAN Au-198 DI TERAS MOLIBDENUM RSG-GAS
Full text linkESTIMASI PANAS GAMMA PADA PRODUKSI RADIOISOTOP Lu-177, Ir-192, DAN Au-198 DI TERAS MOLIBDENUM RSG-GAS. Panas gamma (Gamma heating) merupakan isu penting terkait keselamatan fasilitas iradiasi suatu reaktor dan sampel iradiasinya. Panas gamma dihasilkan dari interaksi energi gamma dengan material target. Energi gamma yang dihasilkan dari reaktor memiliki karakteristik energi gamma yang berbeda yang salah satunya dipengaruhi oleh jenis bahan bakar (jenis teras). Uranium molibdenum (UMo) merupakan bahan bakar masa depan yang memiliki beberapa keunggulan dibandingkan uranium oksida (UO2) dan silisida (USi) salah satunya dapat meningkatkan operasi reaktor. Untuk itu dilakukan studi komputasi panas gamma RSG-GAS dengan bahan bakar UMo pada beberapa proses produksi radioisotop seperti radioisotop Lu-177, Ir-192, dan Au-198. Penelitian ini menggunakan code ORIGEN untuk menghitung energi gamma yang dihasilkan untuk jenis bahan bakar UMo. Estimasi panas gamma menggunakan program Gamset, suatu program didesain dan sudah teruji untuk menghitung panas gamma di RSG-GAS. Hasil perhitungan panas gamma berbahan bakar UMo di RSG-GAS dalam kisaran 4,85 W/g ~ 8,69 W/g . Hasil ini lebih kecil dibandingkan dengan panas gamma pada uranium silisida (USi) yaitu sekitar 9,27 W/g ~ 13,3 W/g. Radioisotop Lu-177 memiliki panas gamma terbesar sekitar 8,69 W/g, yang diikuti oleh Au-198 dan Ir-192 yang masing-masing sebesar 5,89 W/g dan 7,12 W/g. Panas gamma pada ketiga radioisotop yang diproduksi oleh RSG-GAS berbahan bakar UMo tidak melebihi panas gamma maksimum (20 W/g) yang telah ditentukan sehingga dapat diartikan aman untuk reaktor dan sampel.Kata kunci: Panas gamma, UMo, RSG-GAS, radioisoto
Review on Granitic Rocks in Sumatra: Intrusion Process, Classification, Mineralization and Potential Uses
Full text linkGranitic rocks are widely distributed in Sumatra and surrounding areas. These granitoids are classified into several granite provinces of Southeast Asia with different intrusion processes and specific characteristics. This paper aims to review the intrusion of granitic rocks in Sumatra and describe the opportunities associated with it. Granite rocks are used to manufacture cultural heritage, works of art, and ornaments because of their weathering resistance, color diversity, and hardness characters. S-type granite intrusion in Sumatra might be associated with tin mineralization while silver-gold with the I-type. Theoretically, granite contains more REE than other igneous rocks. Mining and extraction difficulties complicate the direct REE exploitation from fresh granite. A-type granite relatively contains more REE than the other types, but this type of granite is not correlated with certain provinces. Indonesia has a tropical climate which is prone to weathering. Therefore, it is possible for REE and/or bauxite enrichments in the granite weathering horizon. Granite is assumed to be a potential source of uranium and thorium, especially for the S-type, because it is formed through the compression of sediments that can absorb these radioactive elements from the continental crust.Granitic rocks are widely distributed in Sumatra and surrounding areas. These granitoids are classified into several granite provinces of Southeast Asia with different intrusion processes and specific characteristics. This paper aims to review the intrusion of granitic rocks in Sumatra and describe the opportunities associated with it. Granite rocks are used to manufacture cultural heritage, works of art, and ornaments because of their weathering resistance, color diversity, and hardness characters. S-type granite intrusion in Sumatra might be associated with tin mineralization while silver-gold with the I-type. Theoretically, granite contains more REE than other igneous rocks. Mining and extraction difficulties complicate the direct REE exploitation from fresh granite. A-type granite relatively contains more REE than the other types, but this type of granite is not correlated with certain provinces. Indonesia has a tropical climate which is prone to weathering. Therefore, it is possible for REE and/or bauxite enrichments in the granite weathering horizon. Granite is assumed to be a potential source of uranium and thorium, especially for the S-type, because it is formed through the compression of sediments that can absorb these radioactive elements from the continental crust
NANORODS ZnO THIN FILM PERFORMANCE AS TRANSPARENT HEATERS.
Full text linkNANORODS ZnO THIN FILM PERFORMANCE AS TRANSPARENT HEATERS. Transparent heaters have been used for various applications. In this research, a transparent heater made from ZnO nanorods has been successfully fabricated. ZnO nanorods were produced by using the chemical bath deposition method.The results of the XRD investigation showed that the ZnO_0.015 and ZnO_0.025 samples contained three and five ZnO peaks, respectively, with a hexagonal wurtzite crystal structure. The crystallite size increased along with the increase in the solution concentration from 71.198 nm to 82.924 nm. The morphological characterization of the samples using FE-SEM showed that ZnO_0.025 sample had a better surface covarege than ZnO_0.015 sample. The average diameters of ZnO_0.015 and ZnO_0.025 are 127.130 and 146.756 nm, respectively. The transmittance value decreased along with the increase of solution concentration which is from 55% to 53%. The value of the band gap energy decreased as the concentration of the seed solution increased from 3.25 eV to 3.20 eV. The resistivity values of ZnO_0.015 and ZnO_0.025 are 1.126 x 10-4 and 0.824 x 10-4Ωcm, respectively. From these results it appears that ZnO_0.025 sample has a more optimal performance as a transparent heater compared to ZnO_0.015 sample
Petrogenesis and Geological Structure of Tantan Granitoid in Sungai Manau District, Merangin Regency, Jambi Province
Full text linkTantan granitoids are Late Triassic–Early Jurassic age intrusive rocks that are quite extensive and can be partially found in Sungai Manau Sub-district, Merangin Regency, Jambi Province. Tantan granitoids are found in the Barisan Hills physiography, a magmatic arc line on Sumatra Island. Tantan granitoids are interesting to observe to explain rock formation. The petrographic and XRF analyses can provide insight into the intrusive rock type, its relationship to the tectonic framework, and magmatism. The trend of potential mineral resources can be interpreted based on the granitoid-type approach. The Tantan Granitoid Intrusion has two types of rocks: granite and quartz monzodiorite. Granite and quartz monzodiorite are sub-alkaline magma types, with the granitoid type being I-type metaluminous, which tends to have potential with base metal minerals associated with hornblende minerals from observations or petrographic analysis. Based on the TAS diagram of Na2O+K2O vs. SiO2 shows that the sub-alkaline magma type is a calc-alkaline series type in the K2O vs. SiO2 diagram and a calc-alkaline type in the AFM diagram. This data analysis shows that the tectonic formation of the Tantan Granitoid magma was formed from orogenic results in the form of a Continental Arc. This type can be associated with Meso-Thetic subduction activities against the West Sumatra Sundablock during the Late Triassic–Early Jurassic. Structures in the study area include northwest-southeast trending horizontal faults, including Batang Tantan Fault, Tiangko Fault, Sei Tengko Fault, and Serik Fault, then northeast–southwest trending regional faults, and relatively downward trending faults, namely Serik Fault and Betung Fault. The formation of fault structures is believed to result from subduction tectonic processes during this period
ASSESSMENT OF OPERATION SAFETY OF THE RSG-GAS REACTOR TO SERVE RADIOISOTOPE TARGET IRRADIATION
No full textThe RSG-GAS multipurpose reactor is operated to serve the utilization in the field of radioisotope production and NAA, material research. The reactor actually has power of 30 MW thermal, but upon considerations of efficiency and of most users requirements, the reactor is mostly operated at the power of 15 MW thermal, 5 days a week to produce a primary radioisotope from target of 2 grams U-235. To guarantee the safe operation and optimum utilization, a safety procedure was established. The paper is intended to assesst the operation safety in serving radioisotope target irradiation at its cycle operation. Assessment was carried out for core numbers 102 – 105. The result shows that excess reactivity and shutdown margin reactivity are safe to provide the target irradiation in the core for each cycle operation.
Analisis Perhitungan Pembangkitan Panas Target Lu2O3 di Teras Reaktor RSG-GAS menggunakan Program GENGTC
Full text linkLutesium-177 (l77Lu) merupakan salah satu radioisotop yang efektif untuk terapi kanker prostat. Radioisotop 177Lu diproduksi dengan cara mengiradiasi target Lu2O3 di teras reaktor RSG-GAS. Untuk keperluan pengendalian keselamatan iradiasi di teras reaktor RSG-GAS, pada iradiasi target Lu2O3 perlu dilakukan beberapa perhitungan, salah satunya adalah perhitungan perpindahan panas target ke pendingin primer kolam reaktor. Panas gamma yang terbangkitkan pada target dan kapsul perlu dibuang ke sistem pendingin reaktor agar tidak mengakibatkan kerusakan target. Profil suhu dari pusat target sampai dinding terluar dari kapsul selama iradiasi dihitung dengan menggunakan program GENGTC (Generalized Gap Temperature Calculator) yang dijalankan dengan program komputer BASIC. Dari hasil perhitungan dihasilkan suhu pada pusat target maupun suhu pada kapsul lebih kecil dari titik lelehnya sehingga integritas target dan kapsul masih terjag