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INDONESIA
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology)
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 280 Documents
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MONTE CARLO SIMULATION FOR THE EFFICIENCY OF THE RGU-1 STANDARD IN URANIUM MEASUREMENT IN SAMPLE DIFFERENT ENVIRONMENTAL MATRIX I Gede Pranawiditia; Rasito Tursinah; Putu Sukmabuana; Badra Sanditya Rattyananda; Novia Agustin; Moh Nurul Subkhi
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 23, No 2 (2022): Agustus 2022
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2022.23.2.6944

Abstract

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.
RANCANG-BANGUN SISTEM PENCUPLIK UDARA MODEL PORTABLE-ADJUSTABLE Dikdik Sidik Purnama; Muhamad Yuyus; Haryo Seno; Rian Fitriana
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 2 (2020): Agustus 2020
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2020.21.2.6939

Abstract

Dalam upaya melindungi pekerja, masyarakat, serta lingkungan, perlu dilakukan monitoring dan pengawasan secara berkala mencakup seluruh aspek keselamatan di lingkungan fasilitas nuklir yang mengacu kepada peraturan perundang-undangan. Monitoring perlu dilakukan untuk mengetahui nilai radioaktivitas komponen lingkungan yang berpotensi berdampak bagi kualitas lingkungan sehingga dijadikan dasar evaluasi pengelolaan lingkungan. Udara merupakan salah satu komponen lingkungan yang dipantau dengan pengukuran secara tidak langsung di laboratorium. Monitoring terhadap komponen udara memerlukan sistem sarana dan peralatan pendukung lainnya. Selain itu, sarana yang ada dinilai kurang praktis mengingat kondisi dan kendala di lapangan. Oleh karena itu, pada tulisan ini dijelaskan mengenai pemenuhan sarana yang diperlukan dengan cara merancang sistem pencuplik udara yang cukup ekonomis, desain model portable-adjustable sehingga selain mendapatkan sarana yang relatif murah, juga memberikan kemudahan untuk dapat meminimalisasi beberapa kendala yang dihadapi di lapangan. Perancangan dilakukan dengan cara mengidentifikasi kendala yang dihadapi di lapangan, menentukan bagian-bagian sistem yang diperlukan, lalu membangun sistem dengan memanfaatkan komponen yang telah tersedia dan mudah didapat di pasaran. Telah dirancang dan dibuat sistem alat pencuplik udara model portable-adjustable. Sistem alat telah dioperasikan dan digunakan untuk kegiatan monitoring komponen udara.
NEUTRONIC ANALYSIS OF DETERMINATION OF FUEL CONFIGURATION FOR HOMOGENEOUS TRIGA 2000 NEW CORE Irsyad Irsyad; Nailatussaadah Nailatussaadah
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 23, No 2 (2022): Agustus 2022
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2022.23.2.6954

Abstract

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.
CALIBRATION TECHNIQUE OF TEMPERATURE MONITORING CHANNEL ISOTOPE PRODUCTION REACTOR Nanda Nagara; Santiko Tri Sulaksono; Rian Fitriana
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 24, No 2 (2023): August 2023
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2023.24.2.6909

Abstract

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 Woro Yatu Niken Syahfitri; Muhammad Bachri Amran; Muhayatun Santoso
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 24, No 2 (2023): August 2023
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2023.24.2.6878

Abstract

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 Prasetyo Basuki; Nuri Trianti; Santiko Tri Sulaksono; Cici Wulandari; Fahma Roswati; Hisyam Zulkarnain; Nina Widiawati; Haryo Seno
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 24, No 2 (2023): August 2023
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2023.24.2.6899

Abstract

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.
INVESTIGATION OF AG AND PD FISSION PRODUCTS PENETRATION DEPTH IN ZRC LAYER OF HTGR TRISO FUEL PARTICLE USING SRIM/TRIM MONTE CARLO SIMULATION Mardiyanto Mardiyanto; Nanda Shabrina; Abu Khalid Rivai
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 24, No 2 (2023): August 2023
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2023.24.2.6859

Abstract

High-temperature gas-cooled Reactors (HTGRs) is one type of Generation IV reactor that uses TRISO (tri-structural isotropic) coated-fuel particles (CFP) for containment of radioactive fission products, which is produced from the fission reaction of UO2 fuel. ZrC has been proposed to be the main barrier for containing fission products either as a replacement of the SiC layer or as an additional layer of the TRISO fuel particle to overcome the corrosion issue of SiC because of interaction with the fission product of silver (Ag) and palladium (Pd). ZrC is an excellent material because it has good physical and nuclear properties, i.e., high corrosion-resistant, excellent thermal shock resistance and a small cross-section for neutron capture. ZrC is expected to provide a better barrier against Ag and Pd diffusion attacks than SiC. However, ZrC is very challenging to manufacture, so it depends on factors such as microstructure, chemical composition and interactions, morphology and impurities. Many attempts have been made to study the interaction phenomena of Ag and Pd with ZrC that cause corrosion. Here, the penetration depth of those two fission products was studied using SRIM (Stopping and Range of Ions in Matter) /TRIM (TRansport of Ions in Matter) for simulation with 0.1-10 MeV of kinetic energies. The results provide detailed information about the Ag/ZrC and Pd/ZrC Ion Ranges and Doses. In addition, Ag and Pd’s products of the depth and concentration within ZrC were observed as important first steps in understanding the corrosion phenomena of her ZrC layers in TRISO particles.
TEMPERATURE MAPPING OF TRIGA 2000 REACTORS AT 500 kW POWER WITH 105 CONFIGURATIONS OF PRE-RESHUFFLING AND POST-RESUFFLING FUEL Reinaldy Nazar
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 24, No 1 (2023): February 2023
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2023.24.1.6970

Abstract

The continuity of operation of the TRIGA 2000 reactor is thermohydraulically determined by the temperature of the fuel and the temperature of the primary cooling water in the reactor core. Currently, the operation of the TRIGA 2000 reactor at a power of 500 kW using a fuel 105 configuration in the core has caused boiling and the formation of bubbles in the reactor core, thereby reducing neutron moderation. The core of reactor is unable to achieve more power. One of the efforts that can be made to reduce the core temperature of the TRIGA 2000 reactor is by reshuffling the fuel inside the core, including using 105 fuels but shifting the position of the fuel to a different ring. In this research, thermohydraulic analysis has been carried out using the FLUENT program package for the configuration of 105 fuels in the pre-reshuffling and post-reshuffling core. Based on the results of the study, it is known that at 500 kW of power with a pre-reshuffling fuel configuration, there are positions for sub-cooled boiling in B3, B4, B5, B6, D4, D6, D8, D10, and D12. The hottest channel is at B5 with a maximum fuel cladding surface temperature of 126.41 °C, and a cooling water saturation temperature in the core of 112.4 °C. Meanwhile, for the post-reshuffling fuel configuration there is no position for sub-cold boiling in the core, where the maximum temperature is at B2 with the maximum fuel cladding surface temperature of 93.55 °C. Thus, it is concluded that the TRIGA 2000 reactor with a configurations of 105 post-reshuffling fuel can be operated at of 500 kW without boiling or at least not occurring sub-cold boiling.
COMPARATIVE ANALYSIS OF COOLANT MASS FLOW RATE FOR PELUIT-40 REACTOR IN ENERGY CONVERSION SYSTEM: A STUDY OF CONCEPTUAL DESIGN WITH AND WITHOUT A SPLITTER Dhiya Salma Salsabila; Ign. Djoko Irianto; Sukmanto Dibyo; Athiek Sri Redjeki
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 24, No 2 (2023): August 2023
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2023.24.2.6903

Abstract

PeLUIt-40 is a nuclear reactor being designed in Indonesia for heat utilizing and generating electricity, with a thermal power of 40 MW. To improve energy efficiency, a system of electricity power and heat generation for hydrogen production called a cogeneration system was developed. The purpose of this study is to determine the best design for the cogeneration system. In this study, two conceptual designs of the cogeneration system were simulated, i.e., with and without a splitter system, respectively. The effect of coolant mass flow rate from (5, 6, 7, 8, 9, 10, 11, 12, 13, and 14 kg/s) to the energy utilization factor were analyzed. Calculations were performed using the ChemCAD 6.4.1 program and Python programming. The result shows that an increase of the coolant mass flow rate will increase the exit temperature of the coolant secondary side as a result of the heat transfer in the Intermediate Heat Exchanger (IHX). This temperature impacts an increase in the thermal power used for power generation and heat production. An increase in the mass flow rate in both designs also causes the value of the energy utilization factor (Energy Utilization Factor-EUF) and the value of the thermal efficiency to increase. Using the splitter has an EUF value of 34.51%, while the without splitter design is 33.92%. Likewise, the efficiency value of both with a splitter and without a splitter are 71.02% and 69.92%.
SIMULATION OF STRATIFICATION BEHAVIOR OF TWO IMMISCIBLE FLUIDS USING FINITE VOLUME PARTICLE (FVP) METHOD Faris Kamal Islahi; Nur Asiah Aprianti; Asril Pramutadi Andi Mustari; Koji Morita
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 24, No 1 (2023): February 2023
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2023.24.1.6751

Abstract

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.

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