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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Science and Technology Indonesia
Miftasani, Fitria
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Biochemistry, Genetics & Molecular Biology Chemical Engineering, Chemistry & Bioengineering Energy Environmental Science Materials Science & Nanotechnology Physics

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Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel Dwijayanto, R. Andika Putra; Miftasani, Fitria; Harto, Andang Widi
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 25, No 3 (2023): October 2023
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2023.6880

Abstract

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.
Corrosion Behavior of Modified F/M Steel with Ti and Dispersed Oxides: Y2O3 and ZrO2 Under High Temperature in Static Liquid Lead Setyo Hadi, Dhimas; Wafda, Hakimul; Pramutadi Andi Mustari, Asril; Trisnawan, Veri; Widiawati, Nina; Miftasani, Fitria; Hadi Prajitno, Djoko
Science and Technology Indonesia Vol. 10 No. 3 (2025): July
Publisher : Research Center of Inorganic Materials and Coordination Complexes, FMIPA Universitas Sriwijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26554/sti.2025.10.3.877-888

Abstract

This study investigates the corrosion resistance of Oxide Dispersion Strengthened (ODS) steel in a lead environment, which is crucial for Lead-Cooled Fast Reactors (LFR), a type of Generation IV nuclear reactor. To improve corrosion resistance, two types of oxides-yttrium oxide (Y2O3) and zirconium oxide (ZrO2)-were added individually and in combination to the ODS steel. The samples were synthesized via powder metallurgy and characterized using optical microscopy, X-ray diffraction (XRD), scanning electron microscopy with energy-dispersive X-ray spectroscopy (SEM-EDX), and Vickers hardness testing. Corrosion testing was conducted in static liquid lead at 550°C for 75 hours. The results showed that the addition of Y2O3 and ZrO2 significantly refines grain structure, increases hardness, and promotes the formation of stable, protective oxide layers. Particularly, the dual-oxide (Y2O3+ ZrO2) sample exhibited the most uniform and effective oxide barrier, indicating improved resistance to lead corrosion. These findings demonstrate that dual-oxide dispersion is a promising strategy for improving the durability of structural materials in LFR applications.
Co-Authors Andang Widiharto Dwijayanto, R. Andika Putra Hadi Prajitno, Djoko Pramutadi Andi Mustari, Asril Setyo Hadi, Dhimas Trisnawan, Veri Wafda, Hakimul Widiawati, Nina