STRENGTHENING PROGRAM FOR NUCLEAR CYBER SECURITY AT NUCLEAR FACILITIES

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

PERBANDINGAN DOSIS PERMUKAAN PADA PEMERIKSAAN THORAX ANAK MENGGUNAKAN METODE AUTOMATIC EXPOSURE CONTROL DAN METODE MANUAL

PERBANDINGAN DOSIS RADIASI PADA PEMERIKSAAN THORAX ANAK MENGGUNAKAN METODE AUTOMATIC EXPOSURE CONTROL DAN METODE MANUAL. Automatic Exposure Control (AEC) pada pesawat sinar-X Digital Radiography (DR) secara otomatis dapat mengendalikan paparan radiasi, sehingga dapat menurunkan Dose Area Product (DAP) mencapai 61% tanpa mengurangi kualitas citra medis. Metode AEC dirancang untuk pasien dewasa, namun tidak menutup kemungkinan digunakan untuk pasien anak. Agar tingkat risiko kanker akibat radiasi pada anak dapat diminimalisasi, maka metode AEC ini menjadi penting untuk diaplikasikan. Dalam penelitian, dilakukan perbandingan metode AEC dan metode manual terhadap 60 pasien anak pemeriksaan thorax untuk memperoleh metode yang memberikan dosis permukaan lebih rendah. Pasien anak dikelompokkan dalam tiga kategori menurut usia, yaitu; 1-5 tahun, 6-10 tahun dan 11-15 tahun. Setiap kategori terdiri atas 10 pasien untuk metode AEC dan 10 pasien untuk metode manual. Pengukuran dosis permukaan menggunakan TLD LiF:Mg,Cu,P. Dari penelitian diperoleh dosis permukaan untuk Kategori-1 masing-masing 0,15±0,09 mSv untuk metode AEC dan 0,15±0,02 mSv untuk metode manual. Untuk Kategori-2 dan Kategori-3 masing-masing diperoleh 0,16±0,07 mSv (AEC), 0,21±0,06 mSv (manual) dan 0,15±0,04 mSv (AEC), 0,31±0,13 mSv (manual) secara berurutan. Metode AEC untuk pasien anak dapat meningkatkan keselamatan radiasi dan menekan kemungkinan risiko kanker

THE VELOCITY MODEL IDENTIFICATION IN EARTHQUAKES PARAMETERS DETERMINATION IN THE NEAR REGIONAL OF THE BANGKA NPP CANDIDATE SITE

Collecting information and earthquake investigation must be carried out to ensure the safety of the nuclear installation candidate site from seismic aspects. Accurate earthquake location data is essential for seismological studies. The accuracy must be improved from the velocity model factor in determining earthquake parameters in a limited number of stations and less azimuth coverage. The study aims to get the most appropriate velocity model for determining earthquake parameters in the near regional of the Bangka NPP candidate site. The study uses earthquake seismic data in Bangka seismic network with variations of the H-S, Crust 2.0, and TPI velocity models to determine earthquake parameters. The most appropriate velocity model is determined based on the comparison with BMKG results and the smallest errors in identifying earthquake parameters. The results show almost the same epicenter and origin time but different earthquake depths. The TPI velocity model best represents the velocity model in the near regional of the Bangka NPP candidate site. TPI falls into the criteria of tectonic earthquake type and most errors (latitude, longitude, and depth) in earthquake parameters determination are the smallest among other velocity models

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

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

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

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

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

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

ANALISIS PENGGUNAAN EMI FILTER 220 VAC/40A SEBAGAI PENYARING DERAU TEGANGAN PADA PERANGKAT DAC-SIK REAKTOR TRIGA 2000 BANDUNG

Perangkat Data Acquisition Computer – Sistem Instrumentasi dan Kendali (DAC-SIK) Reaktor TRIGA 2000 memerlukan suplai tegangan murni tanpa adanya gangguan noise / derau.  Berdasarkan pengamatan tegangan masuk dipre-Amplifier PA15 menggunakan Digital Oscilloscope Tektronik terhadap tegangan yang masuk perangkat DAC, ditemukan adanya lonjakan tegangan hingga 2000-2400 mV yang menyebabkan SCRAM, sedangkan standarnya dibatasi 20 mV.  Lonjakan tegangan yang masuk perangkat DAC dalam orde milivolt (mV) diolah pada blok pengolah sinyal pre-Amplifier PA15 yang sangat sensitif terhadap kenaikan arus dan tegangan meskipun dalam orde mV. Agar reaktor dapat dioperasikan dengan aman dan selamat serta tidak ada gangguan derau ,maka derau tegangan tersebut harus dihilangkan dengan memasang perangkat EMI (Electromagnetic Interface) filter pasif 220VAC/40A yang mampu menangani lonjakan arus sebesar dua kali lebih besar daripada beban arus perangkat DAC-SIK reaktor (5KVA/20A). Dari hasil pengamatan dengan menggunakan Digital Oscilloscope Tektronik pada sistem setelah dipasang EMI filter diperoleh kesimpulan bahwa perangkat ini mampu menurunkan derau hingga 10 kali lipatnya dan reaktor dapat dioperasikan dengan aman dan selamat tanpa adanya gangguan derau tegangan

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

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

CALIBRATION TECHNIQUE OF TEMPERATURE MONITORING CHANNEL ISOTOPE PRODUCTION REACTOR

The measurement of reactor fuel temperature by using Instrumented Fuel Element (IFE) are necessary for monitoring the safety limit of the reactor fuel during operation. This device uses a temperature sensor type K thermocouple-based (Ni-Cr/Ni) and placed at the hottest position of the reactor core (hot channel). Placement in these positions potentially causing damage that can lead to errors reading of the measurement results. Because the reactor safety limits directly related to temperature, then the thermocouple as a sensor, it needs to be calibrated periodically so that the measurement results send the correct value of the measures. In general, every value that is obtained through measurement has some uncertainty, even though a careful execution of the experiment applied. Therefore, the main goal of this paper is to understand the characteristics of the measurement tools by doing a proper calibration method in order to get accurate results

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

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