Jurnal Sains dan Teknologi Nuklir Indonesia
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    279 research outputs found

    NEUTRONIC ANALYSIS OF DETERMINATION OF FUEL CONFIGURATION FOR HOMOGENEOUS TRIGA 2000 NEW CORE

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    A neutronic analysis has been carried out to determine the configuration of fuel for the homogeneous TRIGA 2000 Reactor new core. This analysis is carried out to get the most optimal configuration scenario if all fuels used are fresh fuel by meeting the parameters in accordance with safety requirements where; shutdown margin ≥ $-0.5; Axial and radial Power Peaking Factor is less than 1.25 and 1.60. There are three types of homogenous core in this study that consist of three types of fuel elements; 8.5-20; 12.20 and 20-20. Method that is used in this study is count each fuel element and scenario with MCNP5 codes. Base on configuration scenarios that have been studied, we concluded that homogeneous core with 90 fuel elements with 12-20 type is the optimum one with k-eff= 1.03342

    KAJIAN PENGARUH TEGANGAN LISTRIK TERHADAP KERUSAKAN KOPLING POMPA PENDINGIN SEKUNDER SELATAN REAKTOR TRIGA 2000 BANDUNG

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    Telah dilakukankajian pengaruh tegangan listrik terhadap kerusakan kopling pompa pendingin sekunder selatan, kajian ini dilakukan tujuannya adalah untuk mengetahui apakah tegangan listrik  berpengaruh terhadap  kerusakan kopling pompa, sehingga harus diganti dengan yang baru. Kegiatan penggantiankopling pompa  dilakukan diakhir tahun 2017. Metoda kajian menggunakan Unbalance Voltage, kegiatan dimulai dengan mengukur besaran tegangan listrikdi tiga kabel yaitu(V(R-S), V(R-T), V(S-T))yang telah melewati Molded Case Circuit Breaker (MCCB) dan dua kontaktor, dilakukan selama 2 jam.Untuk mengetahui keseimbangan dari tegangan listrik yang terukur, maka data hasil pengukuran tegangan yang terkumpul, kemudian dihitung menggunakan rumus NEMA Unbalance Voltage. NEMA memberikan rekomendasi: motor dapat dioperasikan secara normal pada kapasitas rated jika unbalance voltage ≤ 1%. Hasil perhitungan nilai persentase unbalance voltage ada yang mencapai nilai sebesar: 2,17%. Hasil tersebut menunjukan bahwa nilai Unbalance voltage pada  pompa pendingin sekunder selatan tidak berpengaruh  terhadap kerusakan kopling pompa tetapi berpengaruh kepada kenaikan suhu motor pompa sehingga menyebabkan  panas yang berlebih (overheatin) Dapat disimpulkan bahwa nilai Unbalance voltage pada panel catu daya listrik system pendingin sekunder bukan sebagai penyebab kerusakan kopling pompa, namun kerusakan kopling disebabkan karena adanya penurunan kinerja akibat umur pakai komponen

    SIMULATION OF STRATIFICATION BEHAVIOR OF TWO IMMISCIBLE FLUIDS USING FINITE VOLUME PARTICLE (FVP) METHOD

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    In this modern era, the need for energy is increasing, and the environmental issues caused by the energy industry are also increasing. Therefore, one of the long-term alternative energy sources is nuclear energy. However, as is well known, there have been many nuclear reactor accidents, such as the Chernobyl, Three Miles Island, and Fukushima reactors. In those cases, there was an accident in the core reactor, especially the melting of the reactor core. One phenomenon is the stratification of the molten metal component of the melted reactor core. Using simulation, this study will discuss the stratification behavior of two immiscible and incompressible fluids. The particle-based simulation method has advantages over the mesh method in simulating free surface conditions and has a lighter computational load. The particle method used in this simulation is the Finite Volume Particle (FVP) method, derived based on the finite volume method by assuming each particle occupies a certain volume. The simulation of the stratification behavior is carried out using three types of fluids, water, cooking oil, and lubricating oil, which are combined into three variations. The stratification simulation results will be compared with the experimental results obtained from the reference. From the simulation results obtained, there is a pattern similar to the experimental results. Simulation data is also processed to obtain the penetration ratio between fluids in each variation and the length of water penetration through cooking and lubricating oil. The results show that the magnitude of the difference in fluid density and viscosity affects the stratification process

    COMPARATIVE AMBIENT NOISE ANALYSIS USING PROBABILITY SPECTRAL DENSITY OF BANGKA SEISMIC NETWORK

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    This 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

    STRENGTHENING PROGRAM FOR NUCLEAR CYBER SECURITY AT NUCLEAR FACILITIES

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    Threats 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

    KAJIAN PENETAPAN NILAI PEMBATAS DOSIS PEKERJA RADIASI DI PSTNT

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    Telah dilakukan Kaji Ulang Penetapan Nilai Pembatas Dosis (NPD) Pekerja Radiasi yang telah berlaku sejak tahun 2014 di PSTNT. Beroperasinya kembali reaktor TRIGA 2000 secara rutin sejak tahun 2017 meningkatkan volume kegiatan laboratorium RISB dan AAN. Peningkatan volume kegiatan tersebut menyebabkan peningkatan terimaan paparan radiasi dan berakibat pada meningkatnya terimaan dosis akumulasi Pekerja Radiasi di PSTNT, sehingga perlu dilakukan kaji ulang terhadap NPD Pekerja Radiasi di PSTNT. Tujuan dari kaji ulang NPD adalah untuk memperbaharui nilai pembatas dosis yang telah ada sebelumnya (15 mSv/tahun). Kaji ulang dilakukan dengan menginventarisasi: jenis kegiatan dengan sumber bahaya potensial di reaktor dan laboratorium radiasi, terimaan dosis pekerja radiasi selama 4 tahun (2015 – 2018) dan membandingkan jenis kegiatan dengan sumber bahaya potensial dengan terimaan dosis pekerja radiasi rata-rata. Peningkatan kegiatan di PSTNT mengakibatkan semakin meningkatnya terimaan dosis akumulasi rata- rata, dosis maksimum tahunan dan dosis kolektif dari tiap bidang di PSTNT. Meningkatnya dosis tersebut menunjukkan kecenderungan Nilai Batas dosis (NBD) dapat dilampaui dan resiko radiasi bagi para pekerja juga akan semakin meningkat. Untuk menurunkan resiko radiasi bagi Pekerja Radiasi maka nilai NBD tidak boleh dilampaui sehingga perlu dilakukan penurunan NPD dari 15 mSv/tahun menjadi 10 mSv/tahun

    MONTE CARLO SIMULATION FOR THE EFFICIENCY OF THE RGU-1 STANDARD IN URANIUM MEASUREMENT IN SAMPLE DIFFERENT ENVIRONMENTAL MATRIX

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    Preliminary 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 analyzed 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

    PRELIMINARY STUDY OF ARSENIC CONTENT AND TOXICITY ASSESSMENT IN RICE FROM INDONESIA

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    Over 50 percent of the world's population consumes rice as a staple food. However, due to natural and anthropogenic activity, heavy metals, particularly arsenic (As), can be found in rice. This has become a worldwide concern because of the high level of consumption of rice and its processed products, as well as the long-term consequences. Information on dietary arsenic exposure in raw and cooked rice and its content quality in Indonesia is limited; however, its availability is essential for estimating toxicity level intake. Therefore, an advanced, accurate, fast, relatively easy, and environmentally friendly arsenic analysis method, such as total X-ray fluorescence (TXRF) and a line equation approach, is needed. It is necessary to evaluate arsenic content and inorganic arsenic (i-As) in rice. The research aimed to assess preliminary dietary arsenic exposure, evaluate rice's inorganic arsenic concentration, and assess toxicity levels. Toxicity level estimation of arsenic exposure was done by determining the hazard quotient (HQ). The results showed that t-As and i-As in rice were 0.071-0.104 mg/kg and 0.050-0.073 mg/kg (wet base), respectively. The mean percentage of i-As reached 70% from the t-As, and the toxicity level of arsenic in cooked rice is low, as shown by the value of HQ < 1. The estimated result indicates no chronic non-carcinogenic effect caused by these samples

    THERMAL POWER CALIBRATION OF TRIGA 2000 RESEARCH REACTOR

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    The thermal power calibration of the TRIGA 2000 research reactor is very important to get the accuracy of power and neutron flux. The TRIGA 2000 research reactor in Bandung has undergone fuel reshuffling and therefore requires thermal power calibration. Thermal power calibration has been conducted by calorimetric method; it is performed at 100 kW – 500 kW using 7 thermocouples connected to a data logger. The computed average power was lower than the indicated power shown in the control room for all power generation. When observing channel 1 for each power generation, a higher precision can be seen at 500 kW since the calibration process was carried out sequentially from 100 kW to 500 kW while the stirring process was continually operated. The treatment led to a uniform temperature distribution over time. Each measurement channel exhibited inconsistent deviations, indicating that certain power levels had better accuracy in some channels compared to others. This demonstrates that the accuracy of power calculations is not determined by the measurement position

    THE ANALYSIS OF LAPSE RATE PROFILE IN THE SITE CANDIDATE OF NUCLEAR POWER PLANT (NPP) AT GOSONG BEACH, BENGKAYANG REGENCY– WEST KALIMANTAN

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    The lapse rate profile in the site candidate for the Nuclear Power Plant (NPP) at Gosong Beach Bengkayang, has been investigated to obtain a description of the lability of the atmosphere and upper air as part of a meteorological aspect safety study in the plan to develop a NPP site. The study of the lapse rate was carried out using air data on the reanalysis of the Global Data Assimilation System (GDAS) by extracting air temperature data at each altitude level so as to obtain a lapse rate of up to 25 km. Daily data was processed during 2021 and transformed in the monthly average profile data to describe the lapse rate profile in January – December 2021. Tropopause was identified with average altitude about 16.6 km and stratosphere at 20.5 km with a lapse rate about -0.21 ℃/100 m. The surface layer to 200 m have lapse rate from 0.7 ℃/100 m - 0.9 ℃/100 m at 00.00 Universal Time Coordinated (UTC) and 0.5 ℃/100 m -0.6 ℃/100 m at 12.00 UT

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