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Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Published by BRIN Publishing
ISSN : 08524777     EISSN : 25280473     DOI : https://doi.org/10.55981/urania
Core Subject :
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir is a scientific publication platform that presents experimental research and development studies on the nuclear fuel cycle, covering radiation physics and chemistry, reactor engineering, nuclear safety and security, nuclear forensics, and radioactive waste management
Arjuna Subject : -
Articles 183 Documents
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INTEGRATION OF SAFETY ANALYSIS USING HAZOPS AND FTA ON PRECIPITATION PROCESS IN URANIUM REFINING AND CONVERSION FACILITY Putra Oktavianto; Ade Saputra; Mu'nisatun Sholikhah
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 1 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.9350

Abstract

Implementation of safety at nuclear facilities must be implemented as well as possible. This is related to safety, especially for operators who carry out the process directly. In the uranium refining and conversion facility, safety analysis using HIRADC has been implemented to support safety in carrying out the process, especially in the uranyl nitrate precipitation process. However, this is not enough to ensure that safety during the precipitation process at the uranium refining and conversion facility can be maintained. To complement the existing HIRADC, another safety analysis is needed. Therefore, HAZOPS and FTA were analysed. This HAZOPS analysis will complement the safety side of the facility using an indicator control system that will automatically eliminate the risk of hazards that occur during the operation of the facility, while the FTA will analyse the causes of failure that can cause accidents so that the causal factors of the accident can be identified. From the results of the HAZOPS analysis, it was found that there was 1 potential hazard that fell into the low risk category, and 11 potential hazards that fell into the medium risk category. While the results of the FTA analysis obtained 15 events that cause product failure in the precipitation tank. From the results of the safety analysis that has been carried out, it can be concluded that HAZOPS and FTA can complement HIRADC to ensure safety can be maintained during the process.
ANALYSIS OF DENSITY, PHASE, AND MICROSTRUCTURE IN U–Mo ALLOYS Saga Octadamailah; Ganisa Kurniati Suryaman; Supardjo Supardjo; Deni Mustika; Juan Carlos Sihotang; Yusuf Gigih Wicaksono; Slamet Pribadi; Boybul; Anissa Isnaini; Ratih Langenati; Dede Sutarya
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 1 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.10793

Abstract

The performance of research reactors heavily depends on the intensity of the neutron flux produced, which is a key factor in reactor efficiency and effectiveness. To enhance the performance of research reactors, high-density fuel is required to increase neutron flux in the reactor core, enabling optimal irradiation processes. One of the most promising fuel candidates is uranium-molybdenum (U-Mo) alloy. This study aims to investigate the properties of U-Mo alloys through a series of characterizations, including density measurements, phase analysis using X-ray Diffraction (XRD), and microstructural observations using a Scanning Electron Microscope (SEM). The density measurements revealed values close to theoretical calculations, with densities of 17.423 g/cm³ for U-7Mo, 17.292 g/cm³ for U-8Mo, and 17.229 g/cm³ for U-9Mo. XRD analysis identified the presence of the γ-U phase with a body-centered cubic (bcc) crystal structure, characterized by diffraction peaks at 2θ angles of 37°, 53°, 66°, and 78°. SEM observations showed a pattern of bright and dark areas, which were further analyzed using Energy Dispersive Spectroscopy (EDS). EDS analysis indicated that the bright areas had a higher concentration of Mo and a lower oxide content compared to the dark areas. These findings suggest that the addition of Mo not only improves the structural homogeneity but also enhances the oxidation resistance of U-Mo alloys.
INFLUENCE OF Mo AND Nb CONTENT ON THE MECHANICAL AND CORROSION PROPERTIES OF AlCrMoNbZr HIGH-ENTROPY ALLOYS FOR NUCLEAR FUEL CLADDING Heri Hardiyanti; Marzuki Naibaho; Budhy Kurniawan; Jan Setiawan; Masno Ginting; Andon Insani; Januar Widakdo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 1 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.11218

Abstract

The effect of varying Mo and Nb content in AlCrMo5%NbZr and AlCrMoNb5%Zr on their mechanical and corrosion properties has been investigated. X-ray diffraction (XRD) analysis revealed the presence of cubic and hexagonal crystal structure, with AlCrMoNb5%Zr exhibiting a higher concentration of hexagonal structures, contributing to improved hardness and corrosion resistance. Scanning electron microscopy (SEM) and energy-dispersive spectroscopy (EDS) confirmed a dendritic morphology with uniform elemental distribution for both samples. Vickers hardness and the corrosion testing shows the AlCrMoNb5%Zr has superior hardness and significantly lower corrosion rate compared to AlCrMo5%NbZr, respectively. These findings suggest that less amount of Nb content enhances mechanical and corrosion properties, making AlCrMoNb5%Zr a potential material for nuclear reactor applications, mainly as fuel cladding material.
DEVELOPMENT OF MATERIALS FOR IMMOBILIZATION OF CESIUM AND CERIUM BASED ON A COMBINATION OF NOCHAR SUPER ADSORBENT AND UNSATURATED POLYESTER FOR PRODUCTION WASTE RADIOISOTOPE 99Mo Risdiyana Setiawan; Purwantiningsih Sugita; Muhammad Farid; Ratiko; Aisyah; Jaka Rachmadetin; Kuat Heriyanto; Yuli Purwanto; Dwi Luhur Ibnu Saputra; Pungky Ayu Artiani
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 1 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.11422

Abstract

This research aims to develop unsaturated polyester-based materials combined with Nochar superabsorbent as radioactive waste immobilization materials. The focus is to lock up radioactive elements such as cesium (Cs) and cerium (Ce), which are used as surrogates for 99Moradioisotope waste. This study evaluates the performance of immobilized materials in adsorbing and stabilizing radioactive elements using various waste loading percentages of 10%, 15%, 20%, and 25%. The characterization results showed that the combination of unsaturated polyester and Nochar was able to absorb the waste effectively without any migration of radioactive elements to the environment, according to the leaching test results. However, based on the compressive strength test, a high increase in waste loading resulted in a decrease in the mechanical strength of the composite. Thus, an optimal waste loading of 20% provides a balance between absorption capacity and mechanical strength. This study demonstrates the potential of using unsaturated polyester and Nochar as safe and effective immobilization materials for radioactive waste, especially in the context of long-term radioactive waste management.
Resrad Parameter Sensitivity Simulation To Ascertain Local Parameters for Safety Assesment on Bangka Island Andry Setiawan; Mersi Kurniati; Dadong Iskandar; Hendra Adhi Pratama; Yuli Purwanto; Zico Pratama Putra
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 2 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.11503

Abstract

Tin slag and waste generated by tin processing often contain Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM), which pose significant radiation hazards to workers, the public, and the natural ecosystem. To mitigate these risks, the development of a dedicated landfill facility is crucial for managing the radiological impact. This study analyzes the implications of storing TENORM waste, both prior to and following the construction of a landfill. The challenge of TENORM management persists, primarily due to the presence of long-lived radionuclides include uranium-238 (U-238), thorium-232 (Th-232), and potassium-40 (K-40), which are often inadequately handled by industry. To address this, a landfill design was proposed and evaluated by software simulation using RESRAD-Offsite 4.0 software. The default parameter values are multiplied by 0.25, 0.5, 1, 1.5, and 1.75. The resulting dose calculations are compared to those using the default value. If the difference is below 10%, it is considered low sensitivity, between 10% and 1000%, medium sensitivity, and above 1000%, high sensitivity. The reserch aim to optimize safety and resource allocation,. From 194 parameters were simulated, with approximately half exerting a significant influence on dose estimations. This study used software simulations to determine the level of influence each parameter has on dose calculations. Parameters who have low sensitivity are soil to plant transfer factor for Th and U, radionuclide spesific release for Th, U, and K, medium sensitivity are precipitation, total porosity saturated zones, high sensitivity are Fraction of time spent on primary contamination at indoor and fraction of time spent for livestock. 
A Review on High-Temperature Steam Oxidation Resistance of Zirconium Cladding Materials Subjected to Plasma Electrolysis Nisa Nashrah; Cahya Krisnawati Marbun; Akbar Ridho Saputra; Juan Carlos Sihotang
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 2 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.12906

Abstract

 Zirconium alloys, such as Zircaloy-4 and ZIRLO, are the standard cladding materials in pressurized water reactors (PWR) due to their low neutron absorption and corrosion resistance. Yet, under loss-of-coolant accident conditions, rapid steam oxidation above 900 °C accelerates hydrogen uptake, embrittlement, and cladding failure. Plasma electrolysis (PE) has emerged as a promising surface modification strategy, directly converting the Zr surface into a ZrO₂-based ceramic layer with strong adhesion, phase stability, and enhanced oxidation resistance. This review provides a comprehensive overview of PE coating formation, emphasizing anodic oxidation, plasma microdischarge, and incorporation of electrolyte-derived elements that tailor microstructure and tetragonal ZrO₂ stabilization. Comparative assessments show that PE-coated claddings delay breakaway oxidation, suppress oxygen diffusion, and maintain structural integrity better than bare alloys or many physical vapor–deposited coatings. The influence of coolant chemistry, irradiation effects, and thermal cycling on long-term coating durability is also evaluated. Remaining challenges include controlling thickness, mitigating phase transformation, and ensuring irradiation stability. Addressing these issues will be critical to realizing PE-coated zirconium as a viable accident-tolerant fuel cladding for advanced nuclear reactors. 
A Critical Review of Radioactive Substances Security Management in Indonesia: Regulatory Framework and Implementation Challenges Based on Actual Incidents Andicho Haryus Wirasapta; Tiara Deta Pamungkas
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 2 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.13399

Abstract

The utilization of radioactive sources in various sectors, including medicine and industry, offers significant benefits to public welfare but also poses serious risks if not managed securely. This review article highlights the urgent need for a comprehensive understanding of radioactive substances security, which is conceptually distinct from radiation safety. The purpose of this review is to critically analyze the change of Indonesia's regulatory framework for radioactive substances security, evaluate the implementation challenges, and formulate policy recommendations based on domestic and international case studies. The methodology employed is a systematic literature review and comparative case study analysis of scientific literature, recent regulations, and incident reports from credible institutions such as the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) and the International Atomic Energy Agency (IAEA). The analysis aims to identify trends, gaps, and causal relationships between policy and practices. It had been found that regulatory framework in Indonesia, particularly through Government Regulation (GR) No. 45 Year 2023 and BAPETEN Regulation (BR) No. 5 Year 2024, has evolved to specifically address security threats. However, implementation faces significant challenges such as insufficient number of human resources and large geographic area. Case studies of the Goiânia incident and the Serpong incident demonstrate that failures in security management can have fatal and widespread consequences. It is concluded that strengthening radioactive substances security management in Indonesia requires not only a robust regulatory framework but also strategic investment in technological innovation, enhancement of qualification and competency personnel, and the establishment of a solid security culture.
Effect of Gamma Irradiation on Crosslink Density and Chemical Characteristics of Gadolinium Oxide-Natural Rubber Vulcanizate Composite Dira Amanda; Tetty Kemala; Jaka Rachmadetin; Sulistioso Giat Sukaryo; Adi Cifriadi; Mohammad Khotib; Kuat Heriyanto; Achmad Ramadhani
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 2 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.13522

Abstract

Natural rubber is a polymer that has been widely used in various industrial applications because of its high flexibility. In this study, vulcanizates were developed from SiO2-reinforced natural rubber with added Gd₂O₃. Vulcanizate composites containing 0, 5, and 10 phr of Gd₂O₃ were fabricated to evaluate the combined effect of inorganic fillers and gamma irradiation. All composites were irradiate with gamma rays at a dose of 100 kGy and were evaluated for their chemical characteristic, swelling behavior, and crosslink density. Fourier Transform Infrared (FTIR) analysis showed that gamma irradiation induces significant structural changes in the natural rubber vulcanizate. These changes were confirmed by the emergence of new absorption peaks assigned to O-H and C=C groups in the FTIR spectra. Swelling and crosslink density measurements showed that gamma irradiation increased the vulcanizate’s crosslink density, indicating the formation of a stiffer polymer network. On average, the crosslink density increased by approximately 11%, accompanied by a 9.07% decrease in swelling. These finding highlight the synergistic role of SiO2 and Gd₂O₃ under gamma irradiation in improving the integrity of natural rubber based composites. 
Determination of the Coral Age from Keraton Buton Fort, Baubau City, Based on 14C Activities Using Liquid Scintillation Counting Method Maming; Muhammad Zakir; Andi Tenrisa'na; Zulfhadyanti Rais; Sitti Syara Ramadani; Ajuk Sapar
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 32 No. 1 (2026): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2026.13606

Abstract

Determination of the age of the corals that make up Keraton Buton Fort based on 14C activity using the LSC (Liquid Scintillation Counting) method has been carried out. The coral samples analyzed were the corals that made up the fort taken from the gate of Keraton Buton Fort and a coral sample from the beach of Makassar Island Baubau, asmodern coral. Sample preparation was carried out physically and chemically using a mixture of NaOH with 30% H2O2, followed by a mixture of HClO4with 30% H2O2, and finally with 5% HCl solution to produce a clean and whiter-looking sample with a weight reduction of 10.5% -15.8%. The carbonate of coral samples was separated as CO2by reaction with 10% HCl and absorption by KOH 1 N solution as K2CO3. The total carbon in the two fort coral sample and modern coral was 0.129, 0.132, and 0.129 grams, respectively, and was obtained through the titration method. The specific activity of 14C in the samples was 13.95 DPM/gC and 14.38 DPM/gC in both fort coral samples, and 15.48DPM/gC in modern coral. The age of the coral samples of Keraton Buton Fort calculated fromthe 14C specific activity data was between 817 ± 0.123 and 565 ± 0.105 years, which is older than the ages of the Keraton Buton Fort according to the historical reviews.
Transient Activation Encapsulation Enables Separation-Free Production of High-Purity 177Lu in the G.A. Siwabessy Medium-Flux Research Reactor Maskur Maskur; Yono Sugiharto; Endang Sarmini; Fransiska Christydira Sekaringtyas; Sulaiman; Aulia Arivin Billah; Lira Aprilia Pujianti; Fani Triyatna; Rien Ritawidya; Muhammad Ridwan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 32 No. 1 (2026): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2026.13640

Abstract

The production of high-purity ¹⁷⁷Lu via the direct (n,γ) route is highly dependent not only on isotopic enrichment of the target material but also on the strategic selection of encapsulation materials to reduce radionuclidic impurities. In order to optimize the production of high-specific-activity ¹⁷⁷LuCl₃, this work combines a double-layer containment system consisting of quartz ampoules (SiO₂) and high-purity aluminum capsules (Al 1070) with an enriched Lu₂O₃target (74% ¹⁷⁶Lu). Irradiation was performed in the RSG-GA Siwabessy reactor (BRIN, Indonesia) at a thermal neutron flux of 2 × 10¹⁴ n·cm⁻²·s⁻¹ for 99 and 193 hours. The target was dissolved in HCl/H₂O₂to form ¹⁷⁷LuCl₃and then characterized for radionuclidic purity using high-resolution gamma spectrometry (HPGe) at 48 hours post-end of irradiation (EOI). The results exhibit that this integrated system produces products without detectable container-derived radionuclidic impurities at 48 h post-EOI: activation products from the quartz (¹⁹O, T½ = 26.47s; ³¹Si, T½ = 2.62 h) and aluminum (²⁸Al, T½ = 2.24 min) containers decayed completely within 24 hours. Under normal HPGe conditions, the metastable isomer ¹⁷⁷ᵐLu (T½ = 160.4 d, σ = 2.85 barn), the sole co-produced radionuclidic species, is present at <1% of total activity at EOI, is not detected spectroscopically from initial state of ¹⁷⁷Lu, which can be clinically negligible during the typical therapeutic window (1–14 days post-production). The specific activity obtained was 11 718 mCi/mg (CV = 5.9%) after 193 hours of irradiation, a level adequate for effective radiolabeling of monoclonal antibodies and peptides in targeted radionuclide therapy, despite the presence of stable Lu carrier. This study demonstrates that the interaction between target chemistry and container physics, rather than irradiation parameters alone, is a critical determinant in producing pharmaceutical-grade ¹⁷⁷Lu that meets international radionuclidic purity standards (>99.9%). This approach provides a scalable, separation-free production model applicable to medium-flux research reactors globally.

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