cover
Contact Name
Hilda Yunita
Contact Email
jurnal@rmpi.brin.go.id
Phone
-
Journal Mail Official
urania@brin.go.id
Editorial Address
Kawasan Sains dan Teknologi (KST) Bacharuddin Jusuf Habibie, Jl. Raya Puspiptek 60, Tangerang Selatan 15310
Location
Kota tangerang selatan,
Banten
INDONESIA
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
Comparative Study of Radiation Hardness in Semiconductor Materials (Si, SiC, GaN, Diamond) for Americium-241 Waste-Based Nuclear Batteries Pribadi Mumpuni Adhi; Millaty Mustaqima
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.2026.14937

Abstract

Using Americium‑241 (Am‑241) radioactive waste from spent smoke detectors as an alpha‑voltaic energy source provides a long‑term power solution for sensors in extreme environments. However, high‑energy alpha particles (5.48 MeV) are inherently destructive to semiconductor crystal structures. This study aims to identify the optimal Wide Bandgap (WBG) material by analyzing energy‑loss mechanisms (stopping power), lattice damage, and device geometry design parameters. SRIM 2013 simulations were performed on Si, SiC, GaN, and diamond targets. The analysis includesion distribution range,electronic and nuclear stopping profiles, the calculation of a Radiation Tolerance Index, and the determination of minimum active thickness (Tmin) based on projected‑range statistics. The results show that diamond exhibits the highest tolerance index of 670, enablingthe thinnest device design (~15 μm). In contrast, silicon requires nearly twice the active thickness (~28 μm) and suffers the most severe structural damage. Silicon carbide (SiC) is recommended as a cost‑effective alternative with a Radiation Tolerance Indexof 593. While diamond is the superior material for space‑constrained applications, SiC offers the best balance between radiation resistance and cost for terrestrial applications.
The Effect of Time in the Anodizing Process on the Coating Characteristics and Corrosion Behavior of Zirconium Metal Manogari Sianturi; Fajar Al Afghani; Frisca Ronauli Batubara; Sri Rahmadani; Romi Saputra
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.2026.15001

Abstract

Zirconium and its alloys are the standard material for nuclear fuel cladding in Pressurized Water Reactors (PWR) due to their low neutron absorption cross-section, excellent mechanical properties, and good corrosion resistance in high-temperature water. However, the operational environment of a PWR imposes severe conditions that can degrade the cladding integrity over time, including oxidation, hydriding, and mechanical damage such as scratching or denting during fuel refueling operations. These surface defects can act as initiation sites for localized corrosion, potentially compromising the primary containment barrier. This study investigates the effectiveness of electrochemical anodizing as a surface modification technique to enhance the performance of Zirconium. The anodizing process was conducted at a constant voltage of 30 V with varying durations of 10, 15, and 20 minutes. The resulting surface characteristics were evaluated using Optical Microscopy, Digital Microscopy for roughness analysis, and X-Ray Diffraction (XRD). Mechanical reliability was assessed via Vickers Microhardness testing, while Corrosion behavior was studied in a 3.5% NaCl solution using Open Circuit Potential (OCP), Potentiodynamic Polarization (PDP), and Electrochemical Impedance Spectroscopy (EIS). The results demonstrated that increasing the anodizing time significantly improved the surface quality, reducing the arithmetic mean roughness Ra from 0.53 μm (10 min) to 0.24μm (20 min). XRD analysis confirmed the formation of a crystalline ZrO2oxide layer. Electrochemical tests revealed a substantial enhancement in corrosion resistance; the corrosion current density icorrdecreased by two orders of magnitude from 12.93 x 10-9A/cm2for the substrate to 0.19 x 10-9A/cm2for the 20-minute anodized specimen. The study concludes that a 20-minute anodizing treatment at 30 V produces a robust, smooth, and highly corrosion-resistant oxide layer suitable for mitigating degradation in nuclear fuel cladding applications.
The Role of Aging-Workforce Management in Maintaining Safety Performance in High-Risk Nuclear Installations Fadly Putrajaya; Hendrian; Kabul Wahyu Utomo; Meutia
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.2026.15044

Abstract

The nuclear industry, as a high-reliability organization, faces serious challenges due to an aging workforce that could affect operational sustainability and safety performance. Although the literature on aging workforce management (AWM) is growing rapidly, empirical evidence linking AWM to safety performance in high-risk nuclear installations, particularly in developing countries, remains limited. This study aims to analyze the role of AWM in maintaining and improving safety behavior in nuclear installations in Indonesia. This study uses a quantitative, cross-sectional survey design with 281 employees from nuclear installations under the auspices of the National Research and Innovation Agency (BRIN). AWM is conceptualized as a multidimensional construct encompassing employee well-being and human resource practices, while safety behavior is measured through the dimensions of safety awareness and safety actions. Data were analyzed using Confirmatory Factor Analysis (CFA) and Structural Equation Modeling (SEM). The analysis results show that AWM has a positive and significant effect on safety behavior (β = 0.607; C.R. = 6.875; p < 0.001), with the measurement and structural models having a perfect fit. These findings confirm that well-being-oriented aging workforce management practices, continuous training, work ergonomics, and career planning can strengthen workers' safety awareness and compliance. Theoretically, this study extends the safety and human factors literature by positioning AWM as a strategic mechanism in maintaining the safety performance of high-risk socio-technical systems. In practice, the study's results provide policy implications for adaptive, sustainable human resource management to ensure the long-term safety of the nuclear industry in developing countries.

Filter by Year

2015 2026


Filter By Issues
All Issue Vol. 32 No. 1 (2026): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 2 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 1 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 30 No. 2 (2024): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 30 No. 1 (2024): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 29 No. 2 (2023): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 29 No. 1 (2023): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 3 (2022): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 2 (2022): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 1 (2022): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 3 (2021): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 2 (2021): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 1 (2021): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 3 (2020): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 2 (2020): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 1 (2020): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 1 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 3 (2018): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (2018): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 1 (2018): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 3 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 2 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 1 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 2 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 1 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 3 (2015): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 2 (2015): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 1 (2015): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir More Issue