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Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology)
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
Articles 5 Documents
Search results for , issue "Vol 24, No 2 (2023): August 2023" : 5 Documents clear
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.
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%.

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