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Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega
Published by Badan Tenaga Nuklir Nasional
ISSN : 1411240X     EISSN : 25279963     DOI : -
Core Subject : Science,
Energy Materials Science & Nanotechnology
Jurnal Teknologi Reaktor Nuklir "TRI DASA MEGA" adalah forum penulisan ilmiah tentang hasil kajian, penelitian dan pengembangan tentang reaktor nuklir pada umumnya, yang meliputi fisika reaktor, termohidrolika reaktor, teknologi reaktor, instrumentasi reaktor, operasi reaktor dan lain-lain yang menyangkut reaktor nukli. Frekuensi terbit tiga (3) kali setahun setiap bulan Februari, Juni dan Oktober.
Arjuna Subject : -
Articles 5 Documents
 1 
Search results for , issue "Vol 26, No 1 (2024): February 2024" : 5 Documents clear
Insider Intervention Model in the Sabotage Attack Scenario of a Nuclear Reactor Facility Andiwijayakusuma, Dinan; Asmoro, Teguh; Mardhi, Alim; Setiadipura, Topan
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 26, No 1 (2024): February 2024
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2024.7008

Abstract

The Physical Protection System (PPS) at nuclear facilities aims to prevent intrusions into nuclear facilities that cause sabotage attacks or illegal theft of nuclear material. The outsider, the insider or a collaboration of both can carry out this intrusive action. In this study, we modelled the insider collaborating with the outsider to carry out nuclear facility attacks using sabotage attack scenarios. The modelling takes the form of insider intervention on two parameters protection elements:the time delay () and the probability of detection (). Insider intervention in delay protection elements might have fatal consequences and drastically reduce the effectiveness of PPS performance. Therefore, PPS designers need to pay more attention to the delay element to anticipate the negative impact of insider intervention on the effectiveness of the PPS.
Techno-Economic Assessment and Optimization of a Standalone System in Sebira Island, Indonesia Farah, Laili; Akhmad, Yus Rusdian; Saryadi, Rezky Mahardika; Mardha, Amil; Mudjiono, Mudjiomo; Nuryanti, Nuryanti; Anzhar, Kurnia; Handayani, Airine Hijrah
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 26, No 1 (2024): February 2024
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2024.7020

Abstract

Nuclear power is known as a baseload generator in central power networks, but its implementation is too large-scale for microgrid applications. Nuclear power as a source of electricity is considered for microgrid applications due to its ability to produce emission-free energy. This research discusses the techno-economic analysis and optimization of a hybrid energy system design on Sebira Island, Indonesia, using a multi-year model in HOMER Pro software. Two scenarios were created: diesel-PV-battery and the second scenario, nuclear-PV-battery, with the baseline system being a diesel generator (DG) only. The research results show that with the optimal use of the nuclear-PV-battery system, the levelized cost of electricity (COE) is $0.128. This value is lower compared to the first scenario with a COE of $0.6577. The CO2 emissions generated in the optimal nuclear-PV-battery system are zero, making this system far more viable than other hybrid system schemes.
Advancements in Accident Tolerance Fuel: A New Horizon in Nuclear Safety Ngarayana, I Wayan; Kurniawan, Rusbani; Rachman, Agus Nur; Nugraha, Eka Djatnika; Ekaranti, Egnes; Andani, Ika Wahyu
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 26, No 1 (2024): February 2024
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2024.7017

Abstract

Accident Tolerant Fuels (ATFs) represent a significant advancement in nuclear safety, offering the potential to mitigate the risks associated with nuclear reactor accidents. This paper provides a comprehensive overview of the development and current state of ATF technology, tracing its evolution and highlighting key technological milestones. Through an analysis of various case studies, we examine the practical application and performance of ATFs in real-world scenarios. Despite the promising capabilities of ATFs, their development and deployment are not without challenges. We delve into the technical, regulatory, and economic hurdles that must be overcome to realize the full potential of ATFs. Looking ahead, we explore the prospects of ATFs, discussing potential advancements and their implications for the nuclear industry. The findings of this paper underscore the transformative role of ATFs in enhancing nuclear reactor safety and charting a new horizon in nuclear technology.
HAZOP-Based Radiological Risk Assessment of Pebble Bed Fuel Handling Systems Kurniawan, Rusbani; Ekaranti, Egnes; Rachman, Agus Nur; Nugraha, Eka Djatnika; Ngarayana, I Wayan; Djunaidi, Zulkifli
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 26, No 1 (2024): February 2024
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2024.7016

Abstract

The High-Temperature Gas-Cooled Reactor (HTGR), a promising candidate for Generation IV nuclear reactors, boasts superior inherent passive safety features and a continuous fuel handling system. This system employs multi-pass cycles, utilizing pneumatic and gravitational mechanisms to feed, circulate, and unload the pebble bed fuel element. This paper presents a descriptive analysis assessing the safety risk of the fuel handling system design in HTR-10. The Hazard and Operability Study (HAZOP) methodology is employed to identify hazard parameters, deviation limitations, causes, impacts, and potential risks to the system’s main components. The establishment of probability scales, consequence criteria, risk level ratings, and control activities adheres to the ISO 31000 standard. Primary data were gathered through expert interviews, while secondary data were sourced from design layout documentation, literature reviews, and safety analysis reports. Six main components - the elevator, core, singulator, failed fuel separator, burnup measurement, and distributor - were selected as assessment nodes from the piping and instrumentation diagram. The assessment revealed that each node initially presented a moderate to extreme risk potential (risk level rating C to E). However, after applying the effectiveness index of the designed control, the residual risk for all nodes was reduced to an acceptable limit (risk rating A - very low). Therefore, the fuel handling system design already incorporates adequate control activities to mitigate potential safety risks due to system component failure. As safety risk assessment is dynamic, it should be reviewed periodically or whenever there are design changes at any project stage. This ensures the safety risk magnitude is consistently known and managed effectively.
Evaluation of Pixelated Plastic Scintillators Coupled to Multi-Channel Silicon Photomultipliers for Beta-Ray Detection and Source Localization Rachman, Agus Nur; Kurniawan, Rusbani; Ekaranti, Egnes; Wahyudi, Wahyudi; Nugraha, Eka Djatnika; Ngarayana, I Wayan; Hamdan, Moh
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 26, No 1 (2024): February 2024
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2024.7015

Abstract

This paper presents a novel detector design for radiation detection technology, based on pixelated plastic scintillators coupled to multi-channel silicon photomultipliers (SiPMs). This detector combines the efficiency of plastic scintillators with the sensitivity and versatility of SiPMs, Overcoming the limitations of traditional photomultiplier tubes in terms of durability, power consumption, and sensitivity. The compact and modular nature of the detector makes it suitable for diverse environments and applications, such as portable radiation monitoring devices or integration into existing experimental setups. The performance of the detector was evaluated using beta-ray sources of 36Cl and 90Sr, and it was demonstrated that the detector can detect and localize the point source with high accuracy and resolution.

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