Badan Tenaga Nuklir Nasional: Jurnal BATAN
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ANALYSIS ON HEAT LOSS IN WATER HEATING TANK BASED ON TEMPERATURE SETTING VARIATION DURING NATURAL CIRCULATION FLOW USING FASSIP-02 TEST LOOP
Full text linkBased on the nuclear reactor accident in Fukushima due to an earthquake that caused a tsunami that turned off the electrical system for the cooling water pump. So that the reactor core melts due to the failure of the active cooling system, based on this incident, a passive cooling system that does not require external energy for emergency cooling is needed to prevent such an accident. Experimental research on the passive cooling system based on natural circulation flow to improve reactor thermal management performance during an accident has been done using the FASSIP-02 Test. One of the important components of the simulation of heat sources in nuclear power plants is the water heating tank (WHT). This study aimed to obtain the analysis results of heat absorption in water in WHT and the value of heat loss. The research method was carried out by calculating changes in the internal energy of water in WHT and heat loss for variations in water temperature settings from temperatures of 40 oC, 50 oC, and 60 oC in WHT at steady-state conditions for 5 hours experiment. The results showed that the entire surface of the tank resulted in heat losses of 10.85 kW, 9.2 kW, and 8.37 kW, which occurred at temperature settings of 40 oC, 50 oC, and 60 oC as a whole
STRENGTHENING PROGRAM FOR NUCLEAR CYBER SECURITY AT NUCLEAR FACILITIES
Full text linkThreats to the safety and security aspects of a facility target the physical aspects and the cyberinfrastructure. Critical facilities such as nuclear facilities use cyber-physical systems in their operating systems has vulnerabilities. Nuclear facilities in Indonesia could become targets of cyberterrorism because there have been incidents of attacks in several countries related to nuclear terrorism for specific purposes that threaten the safety and security operations of nuclear facilities. Similar threats may occur at other nuclear facilities as well as nuclear facilities in Indonesia, including the nuclear facility in Indonesia. The purpose of this study is to propose a nuclear cybersecurity program with a qualitative approach to attract more attention in supporting the anticipation of increasing cybersecurity threats at nuclear facilities. The program proposed was based on the description of terminology in nuclear safety and security and literature studies describing incidents of nuclear cyberterrorism attacks in the past. A cyber nuclear security program has been proposed through stakeholder collaboration, resource support, and capacity building for the ongoing nuclear security program
COMPARATIVE AMBIENT NOISE ANALYSIS USING PROBABILITY SPECTRAL DENSITY OF BANGKA SEISMIC NETWORK
Full text linkThis study analyzes the characteristics of ambient noise from four micro-earthquake observation stations located on Bangka Island nuclear power plant site. The analysis was performed using the PSD (Probability Spectral Density) method available in Obspy python-based library. Based on the observational data, the accuracy level at the four observation stations on Bangka Island is under the New High Model Noise (NHNM). Analysis was performed by comparing the 2021 and previous studies using 2014 data. An appropriate noise model as suggested by McNamara and Buland (2004) was developed using Obspy python-based library. At the period range of 0.1-1 sec, most of the station exhibits good performance. The noise level at periods 1-10 sec developed a decreasing pattern along with higher periods. At a period larger than 10 sec, 2021 data shows a better performance compared to the 2014 data
STUDY OF PLUTONIUM UTILIZATION IN AP1000 REACTOR USE SRAC2006 AND JENDL 3.3 NUCLEAR DATA LIBRARY
Full text linkPreliminary Study of Plutonium Utilization in AP1000 Reactor Use SRAC 2006 and JENDL 3.3 has been conducted. Nuclear energy, especially for nuclear reactor, become important this day because the need of energy will increase along with the increasing of human population, the advanced technology and economic. The more nuclear reactor operated the more existence of plutonium stockpile. This study evaluated the standard of Westinghouse AP1000 reactor and ZrB2 as Integral Fuel Burnable Absorber (IFBA). Different fuel compositions of assembly type were analyze in by using SRAC 2006 code system with JENDL 3.3 nuclear data library. This study aiming to compare the neutronics characteristics of an UO2 and an (U,Pu)O2 assembly designs. Some results of the study show that optimal criticality of the fuel assembly can be accomplished by using 5% enrichment of U-235 for UO2 fuel and 9% plutonium fraction for (U,Pu)O2 fuel assembly
Tectonic Structure of Northern Sumatra Region Based on Seismic Tomography of P and S Wave Velocity
Full text linkThe tectonic setting of Sumatra Island is strongly influenced by the oblique subduction of the Indo-Australian Plate, which subducts the Eurasian Plate at a speed of 52–60 mm/year. The movement of these plates resulted in the Northern Sumatra region having seismic sources from tectonic and volcanic activity. The data used in this study is in the form of seismic wave travel-time recorded by numerous seismic stations in the research area from January 2012 to December 2020. The data comes from 5,003 earthquakes recorded by the BMKG seismic network. The inversion is a simultaneous inversion between seismic velocity models (Vp and Vs) and hypocenter parameters by applying a double-difference seismic tomography algorithm. Tomogram results in parts of Aceh (Singkil and Subulussalam) and North Sumatra (Pakpak Bharat and Dairi) at a depth of 0 km show negative perturbations in Vp and Vs values and high Vp/Vs values. The anomaly is most likely related to cracks in fluid-saturated rocks. The tomograms in the south of Lake Toba at depths of 30 km and 40 km have high Vp and Vs perturbation values and low Vp/Vs values. This anomaly indicates a magma supply line that is no longer active or has cooled for a long time. Based on the seismic tomography modeling results, the subducted Indo-Australian Plate to the Eurasian Plate is visible in the study area
Prediction of Potential Acid Mine Drainage Formation in High Sulfidation Epithermal Deposit using Geochemical and Mineralogy Approaches
Full text linkIdentification of acid mine drainage (AMD) can be predicted using a geochemical and mineralogy characterization approach to identify rocks forming and neutralizing acids. Geochemical characterization using static and kinetic tests. The static test is the first step to determining the potential for acid formation in rocks by comparing the potential for forming and neutralizing acids, which are characterized by uncertain behavior that causes predictions to be inaccurate. Kinetic tests were carried out to predict the long-term acid-producing potential better. Furthermore, mineralogical characterization is needed to assess the importance of sample mineral content in predicting AMD. Tests were conducted on rock samples from high sulfidation epithermal (HSE) deposits in North Sulawesi, Indonesia. The samples represent the different geological domain conditions found in HSE deposits. The main acid-producing components are pyrite and secondary minerals (alunite) capable of buffering acidity. The results showed a lower change in leachate pH (from day 30 to 180) and were accompanied by the release of species (high dissolved metals).Identification of acid mine drainage (AMD) can be predicted using a geochemical and mineralogy characterization approach to identify rocks forming and neutralizing acids. Geochemical characterization using static and kinetic tests. The static test is the first step to determining the potential for acid formation in rocks by comparing the potential for forming and neutralizing acids, which are characterized by uncertain behavior that causes predictions to be inaccurate. Kinetic tests were carried out to predict the long-term acid-producing potential better. Furthermore, mineralogical characterization is needed to assess the importance of sample mineral content in predicting AMD. Tests were conducted on rock samples from high sulfidation epithermal (HSE) deposits in North Sulawesi, Indonesia. The samples represent the different geological domain conditions found in HSE deposits. The main acid-producing components are pyrite and secondary minerals (alunite) capable of buffering acidity. The results showed a lower change in leachate pH (from day 30 to 180) and were accompanied by the release of species (high dissolved metals)
A SIMULATION OF IRRADIATION CALCULATIONS ON LUTETIUM-177 PRODUCTION IN RSG-GAS USING U3SI2-AL AND U9MO-AL FUELS
Full text linkThis research is a simulation of irradiation calculations on the production of the radioisotope Lutetium-177 (177Lu) in the G.A Siwabessy Reactor (RSG-GAS). This study aims to analyze the comparative calculation of 177Lu activity and its purity. One of the production methods of 177Lu in RSG-GAS is carried out by irradiating Lu2O3 targets. This Lu2O3 target irradiation produced the radioisotope 177Lu along with 177mLu as an impurity. For Medical treatment using radioisotopes, the minimum activity for 177Lu is 20 GBq/mg, and the impurity should not exceed 0.1%. Calculations were carried out with thermal neutron flux input at 15 MWt operational power for the RSG-GAS core with U3Si2-Al fuel (density 2.96 gU/cc and 3.55 gU/cc) and U9Mo-Al fuel (density 3.55 gU/cc). Calculations were carried out by simulating 8 days of irradiation using ORIGEN2.1. The results showed that the 177Lu activity resulting from irradiation of Lu2O3 targets at various CIP positions in the U9Mo-Al reactor core was larger than that of the U3Si2-Al core. Until the 30th day, the 177Lu product resulting from irradiation on the U3Si2-Al and U9Mo-Al cores still meets the minimum value of 20 GBq/mg for treatment needs in nuclear medicine, with the activity value of 177Lu resulting from irradiation on the U3Si2-Al core ranging from 241-403 GBq/mg, while the activity of irradiated 177Lu in the U9Mo-Al core ranges from 335-561 GBq/mg. In addition, until the 30th day of decay, 177Lu has a percentage value of 177mLu irradiated in the U9Mo-Al and U3Si2-Al cores of 0.0346% and 0.0344%, respectively. The results are still below the maximum impurity value of 0.1% and thus safe to use as a therapeutic agent. Keywords: 177Lu, Activity, RSG-GAS, ORIGEN2, Irradiatio
POTENSI LINGKUNGAN KAWASAN NUKLIR SERPONG DAN EVALUASI KESELAMATAN UNTUK TAPAK FASILITAS BOREHOLE DISPOSAL LIMBAH SUMBER RADIASI BEKAS
Full text linkPenyimpanan lestari terhadap sumber radiasi bekas (disused sealed radioactive sources = DSRS) masih menghadapi beberapa rintangan, antara lain karena DSRS umumnya berumur paro panjang, tingkat radiasi gamma-photon tinggi, sulitnya opsi untuk dikembalikan ke negara pembuat, dan aktivitas melampaui batas untuk shallow land disposal. Untuk itu perlu dikembangkan sistem penyimpanan lestari limbah DSRS dengan fasilitas skala kecil yang ekonomis, memenuhi standard keselamatan pekerja, masyarakat dan lingkungan. Jawaban untuk masalah ini adalah dengan konsep penyimpanan lestari dalam lubang bor (borehole disposal = BHD). Penelitian ini fokus pada evaluasi potensi lingkungan Kawasan Nuklir Serpong (KNS) untuk tapak fasilitas BHD dan keselamatannya sesuai dengan standar IAEA yaitu borehole disposal of disused sealed sources (BOSS). Evaluasi lingkungan KNS dilakukan dengan karakterisasi dan evaluasi keselamatan lingkungan geologi dan non geologi untuk tapak BHD sesuai standard IAEA. Secara umum, hasil evaluasi parameter lingkungan terhadap kriteria tapak disposal menunjukkan adanya kesesuaian. Namun ada beberapa parameter yang perlu diberikan solusi teknologi (engineered barrier) agar fungsi tapak sebagai natural barrier dapat terpenuhi. Beberapa solusi teknologi tersebut meliputi kemasan limbah (kapsul dan kontainer), buffer dan backfill material, pelapis lubang bor (casing), pemasangan basement plug dan upper/cover plug. Hasil dari pengkajian keselamatan dengan Borehole Disposal Concept (BDS) scoping tools menunjukkan bahwa konsep fasilitas BHD pada tapak KNS termasuk dalam zona hijau (green zone) yang berarti aman, dengan nilai total dosis maksimal sebesar 7.2e-9 Sv/y di tahun 46.678y. Menggunakan system standar BOSS dengan penambahan engineered barrier maka lokasi tapak di KNS memenuhi kriteria dan berpotensi untuk penempatan fasilitas borehole disposal limbah DSRS.Kata kunci: potensi, lingkungan, tapak, keselamatan, borehole disposal
ADSORPSI URANIUM MENGGUNAKAN Na DAN Zr – MONTMORILLONITE
Full text linkMontmorillonite dapat dimanfaatkan sebagai alternatif pengolahan limbah uranium secara adsorpsi. Kation pada interlayer montmorillonite dapat digunakan untuk pertukaran ion dengan uranium. Limbah cair uranium berasal dari sisa proses ekstraksi uranium untuk pengambilan radioisotop molibdenum-99 dan juga pada proses pelarutan yellow cake yang masih mengandung sedikit uranium. Tujuan penelitian ini adalah memodifikasi Na-montmorillonite dengan penambahan zirconium(IV) oxychloride octahydrate (ZrOCl2.8H2O) untuk meningkatkan efisiensi adsorpsinya terhadap uranium. Modifikasi montmorillonite dikarakterisasi dengan XRD dan XRF. Kinetika adsorpsi uranium ditentukan dengan variasi waktu kontak 10, 30, 60, 120, 180, 300, 360, 420 dan 480 menit kemudian ditentukan laju kinetika adsorpsi pseudo orde pertama dan orde kedua. Efisiensi adsorpsi uranium optimum ditentukan dengan variasi pH 3, 5, 7 dan 9. Hasil kurva plot pseudo orde pertama dan orde kedua menunjukan bahwa Na dan Zr-montmorillonite berada pada plot orde kedua dengan konstanta (k2) adalah 0,000354 dan 0,000458 (g/mg.min). Adsorpsi uranium oleh Na-montmorillonite terjadi pada pH 5 sebesar 93,68 % dan Zr-montmorillonite pada pH 7 sebesar 96,52%. Zr–montmorillonite diperoleh nilai Kd masing-masing sebesar 23,42x103 dan 48,26x103 mLg. Modifikasi Zr dapat meningkatkan efisiensi dan kinetika adsorpsi uranium sehingga berpotensi sebagai alternatif adsorben untuk pengolahan limbah uranium cair.Kata kunci: Adsorpsi, Na-montmorillonite, Zr-montmorillonite, zirconium(IV) oxychloride octahydrate, larutan uraniu