https://jurnal.batan.go.id/index.php/tridam/issue/feedJURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA2023-12-07T12:32:43+07:00Tukiran Surbaktituki002@brin.go.idOpen Journal Systems<p style="font-size: 13px;"><strong><em>Jurnal Teknologi Reaktor Nuklir</em> (Journal of Nuclear Reactor Technology) TRI DASA MEGA </strong> provides an international medium for the communication of original researches, ideas and developments in the field of nuclear reactor technologies and applications. Its scope embraces reactor physics, reactor thermal hydraulics, reactor instrumentation, reactor operation, safety analysis, and other fields related to nuclear reactor applications. The journal also publishes review papers that have a <strong>significant review element</strong>, which may take the form of a critique, comparison, or analysis. <br /> <br /> All papers should be written in a clear and concise American English. The submitted paper should follow the <a href="https://docs.google.com/open?id=15hbJI6AcWNFVnwAebQMnz-v582dvjByf" target="blank"> <strong> Template </strong> </a> provided. Please also see our <a href="https://docs.google.com/open?id=1fCojsD4eoimyJYhvZpl7s04RF3ZXiPIA" target="blank"> <strong> Writing Guideline </strong> </a> for information on writing an article suitable for the journal.</p><p style="font-size: 13px;"><strong>All articles submitted to the editorial board shall pass similarity check by <em>iThenticate</em></strong>. To be further reviewed by reviewers, the similarity level of the article must be <strong>less than 25%</strong>.</p><p style="font-size: 13px;">The journal is consistently published three times a year in <strong>February</strong>, <strong>June</strong>, and <strong>October</strong> by The Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency of Indonesia (BATAN).</p>https://jurnal.batan.go.id/index.php/tridam/article/view/6993Editorial Board2023-12-07T12:32:27+07:00Editor In Chieftuki002@brin.go.id<ul><li>Editorial Board</li><li>Peer Reviewer</li><li>Table of Contents</li></ul>2023-11-21T08:28:14+07:00Copyright (c) 2023 JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGAhttps://jurnal.batan.go.id/index.php/tridam/article/view/6880Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel2023-11-21T08:30:28+07:00R. Andika Putra Dwijayantorand002@brin.go.idFitria Miftasanifitriamiftasani.brin@gmail.comAndang Widi Hartoandangwh@ugm.ac.id<table width="643" border="0" cellspacing="0" cellpadding="0"><tbody><tr><td valign="top" width="397"><p>The accumulation of spent nuclear fuel (SNF) is presently considered as a hindrance of the massive deployment of nuclear power plant, especially regarding the transuranic (TRU) elements. Eliminating TRU through transmutation is one of the most feasible alternative as a technical solution to solve the issue. This study explores the possibility of TRU transmutation using molten salt reactor (MSR) in a heterogeneous configuration, where a solid TRU is coated inside the fuel channel filled with liquid salt fuel. Such configuration is proposed to allow higher TRU loading into fluoride salt mixture without compromising the safety of the reactor. TRU coating was applied in consecutively outward radial fuel channel layers with coating thicknesses of 2.5 mm and 5 mm. Calculation was performed using MCNP6.2 radiation transport code and ENDF/B-VII.0 neutron cross section library. From the results, TRU coating with smaller thickness and positioned closer to the centre of the core exhibit higher transmutation efficiency due to exposure to higher neutron flux. Highest transmutation efficiency was achieved at 67.93% after 160 days of burnup. This shows a potential of achieving highly efficient TRU using heterogeneous configuration in MSR core.</p></td></tr></tbody></table>2023-11-21T08:28:14+07:00Copyright (c) 2023 JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGAhttps://jurnal.batan.go.id/index.php/tridam/article/view/6925Study of Alternative Radiation Material Shielding for Gamma Radiation using Monte Carlo Simulation2023-11-21T08:30:28+07:00Gusti Atika Urfagusti.urfa@ulm.ac.idTotok Wiantogusti.urfa@ulm.ac.idTetti Novalina Manikgusti.urfa@ulm.ac.idAmar Vijai Nasrullohgusti.urfa@ulm.ac.id<p>Lead as the most commonly used material for radiation shielding but possessing toxic properties. This research aims to identify alternative, lead-free, and non-toxic materials for gamma radiation shielding through Monte Carlo simulations. Bismuth Oxide (Bi2O3), Barium Oxide (BaO), Tungsten Trioxide (WO3), Tungsten Dioxide (WO2), and Molybdenum Trioxide (MoO3) were selected as potential substitutes for lead. Pure lead (Pb) and Lead Oxide (PbO) were used for comparison. The simulation were performed using Particle Heavy Ion Tracking System (PHITS) software, with a gamma energy of 662 keV. The result of the simulation shows that the linear attenuation coefficient values for Pb and PbO were 0.902 mm-1 and 0.74 mm-1, respectively. Meanwhile, the simulation results of those simulated materials that are closest to Pb and PbO are Bi2O3 and WO2 with an attenuation coefficient of 0.71 mm-1. This simulation shows that for non-lead materials, BiO2 and WO2 have potential as alternative of non-lead radiation shielding.</p>2023-11-21T08:28:15+07:00Copyright (c) 2023 JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGAhttps://jurnal.batan.go.id/index.php/tridam/article/view/6932An Approach for Integration of User Requirement and Anthropometry Data in The Process Design of Reactor Main Control Room2023-11-21T08:30:28+07:00Muksin Aji Setiawanmuks006@brin.go.idSigit Santososigi005@brin.go.idTulis Jojok Suryonotuli002@brin.go.idKiswanta Kiswantakisw002@brin.go.idAnik Purwaningsihanik002@brin.go.idRestu Maeranirest004@brin.go.idAdhika Enggar Pamungkasadhi011@brin.go.idDian Fitri Atmokodian024@brin.go.idDhanu Dwiardhikadhan003@brin.go.idThe construction of a Nuclear Power Plant (NPP) using Small Modular Reactor (SMR) technology is an interesting scheme to support Net-Zero Carbon Emission. The SMR design is an advanced generation reactor with high safety and utilization features, especially the electricity needed and industry. Its modular size can also be applied to remote areas with lower construction costs compared to other types of power plants. Considering the geographical location and territory of Indonesia which is an archipelagic country, this type of reactor is suitable for application in Indonesia. To ensure safety and increase mastery of technology, it is necessary to create a simulator to support this program. Nonetheless, specific regulations govern human-machine interactions (HMI) which is covering the nuclear reactor simulators in Indonesia is not yet available. The research carried out is a review of the regulations that have been implemented in other countries, then provides a choice of operator condition designs, which are adjusted to the average size of Indonesian by considering anthropometric aspects and ergonomic aspects.2023-11-21T08:28:15+07:00Copyright (c) 2023 JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGAhttps://jurnal.batan.go.id/index.php/tridam/article/view/6934The Development Process of Human Machine Interface of Plant Protection System of a Small Modular Reactor2023-11-21T08:30:28+07:00Tulis Jojok Suryonotuli002@brin.go.idSigit Santosotuli002@brin.go.idRestu Maeranituli002@brin.go.idPandhu Ardita Dharma Pratamatuli002@brin.go.idThe Plant Protection System (PPS), which consists of Reactor Protection Systems (RPS) and Engineered Safety Actuated Systems (ESFAS), is one of the most important safety systems in nuclear reactors, including Small Modular Reactors (SMRs). The RPS generates a signal to trip the reactor if the measured reactor parameters exceed the trip setpoint, and then the ESFAS is actuated to mitigate the consequences of the accident by minimizing fuel damage and radioactivity release into the environment. Therefore, a comprehensive Human-Machine Interface (HMI) is essential for monitoring and controlling the PPS to ensure its reliability and enhance the operators' situational awareness. This study discusses the development process of the HMI for the digital PPS of an SMR. In this study, various standards, guidance, and design criteria for PPS and HMI are incorporated and applied to ensure that the proposed design meets the required level of reliability. In the first stage, the proposed design is intended for assessing the functionality and reliability of the PPS. Moreover, in the future, it will play an essential role in the design phase of the HMI for the PPS of an SMR in Indonesia.2023-11-21T08:28:16+07:00Copyright (c) 2023 JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGAhttps://jurnal.batan.go.id/index.php/tridam/article/view/6963The Study of Multiaxial Loading and Damage to the Structure and Materials in the PWR Steam Generator of Nuclear Reactor2023-11-21T08:30:28+07:00Muhammad Subhansubhanbatan@gmail.comTresna Priyana Soemarditsoemardi@eng.ui.ac.idTopan Setiadipurasubhanbatan@gmail.comFarisy Yogatama Sulistyofari016@brin.go.idHana Subiyahsubhanbatan@gmail.com<p>In Pressurized Water Reactor (PWR) Nuclear Power Plants (NPPs), the steam generator is crucial for transferring heat from the primary to secondary cooling systems, vital for steam production to drive turbines, and central to nuclear power safety. This study explores recent research on multi-axial loading, structural integrity, and material durability in PWR steam generators, shedding light on key factors affecting these systems. Common corrosion-related degradation in steam generators often arises from design, material, and water chemistry factors. However, the shift to All Volatile Treatment (AVT), the development of advanced material alloys, and enhanced water quality control in primary and secondary systems have significantly reduced instances of steam generator degradation. These findings promise to enhance the reliability and safety of steam generators in future nuclear applications.</p><p> </p>2023-11-21T08:28:16+07:00Copyright (c) 2023 JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGAhttps://jurnal.batan.go.id/index.php/tridam/article/view/6994Acknowledgement2023-12-07T12:32:43+07:00Editor In Chieftuki002@brin.go.id<ul><li>Abstract Collection</li><li>Keywords Index</li><li>Acknowledment</li></ul>2023-11-21T08:28:17+07:00Copyright (c) 2023 JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA