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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 5 Documents
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Search results for , issue "Vol 23, No 2 (2022): Agustus 2022" : 5 Documents clear
STRENGTHENING PROGRAM FOR NUCLEAR CYBER SECURITY AT NUCLEAR FACILITIES Dikdik Sidik Purnama; Mokhamad Hendayun; Barito Mulyo Ratmono; Poppy Setiawati Nurisnaeni; Satriani Aga Pasma; Rahmat Khatib Purnama
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.2022.23.2.6785

Abstract

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.
COMPARATIVE AMBIENT NOISE ANALYSIS USING PROBABILITY SPECTRAL DENSITY OF BANGKA SEISMIC NETWORK Dima Agusdiansyah; Yuliastuti Yuliastuti; Theo Alvin Ryanto; Akhmad Muktaf Haifani; Nurlaila Nurlaila
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.2022.23.2.6788

Abstract

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.
STUDY OF PLUTONIUM UTILIZATION IN AP1000 REACTOR USE SRAC2006 AND JENDL 3.3 NUCLEAR DATA LIBRARY Nailatussaadah Nailatussaadah; Abdul Waris; Puguh Andik Prastyo
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.2022.23.2.6943

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 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.
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.
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.

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