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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Computational and Experimental Research in Materials and Renewable Energy (CERiMRE) Sustainability Science and Resources
Dwijayanto, R. Andika Putra
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Agriculture, Biological Sciences & Forestry Computer Science & IT Energy Environmental Science Materials Science & Nanotechnology Physics Social Sciences

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Neutronic Analysis of LEU-started Molten Chloride Fast Reactor without Fuel Reprocessing Dwijayanto, R. Andika Putra; Harto, Andang Widi
Computational And Experimental Research In Materials And Renewable Energy Vol 4 No 1 (2021): May
Publisher : Physics Department, Faculty of Mathematics and Natural Sciences, University of Jember

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.19184/cerimre.v4i1.24962

Abstract

One of the rarely explored molten salt reactor (MSR) designs is the molten chloride fast reactor (MCFR). This MSR design employs chloride salt instead of fluoride and operated in a fast spectrum. MCFR brings all the advantages of an MSR including breeding whilst being able to burn plutonium and minor actinides efficiently. Since not many countries have access to civilian plutonium, MCFR can also be started using low-enriched uranium (LEU). This study is an initial neutronic analysis of an MCFR using LEU as its startup fuel. Parameters analyzed are conversion ratio (CR) and its neutronic safety, namely effective delayed neutron fraction (βeff), temperature coefficient of reactivity (TCR), and void coefficient of reactivity (VCR). The core is divided into Core Zone and Blanket Zone. The fuel composition of NaCl-UCl3 with a molar fraction ratio of 60:40 and 50:50 is used in Core Zone and Blanket Zone, respectively. The neutronic calculation is performed using MCNP6 code with ENDF/B-VII library. For reference geometry, CR is valued at 0.9298, βeff at 0.00731, TCR at -19.8 pcm/°C, and average VCR at -154.31 pcm/void%. Thereby, the MCFR fulfills inherent safety criteria. Although its value is remarkably high, CR can be further optimized by modifying the separator and reflector material.
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.
The Sustainability of Nuclear Fuel Resources in Indonesia with Open and Closed Fuel Cycle Dwijayanto, R. Andika Putra
Sustainability Science and Resources Vol. 4 (2023): Sustainability Science and Resources
Publisher : The Indonesian Forestry Certification Cooperation

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55168/ssr2809-6029.2023.4004

Abstract

In the wake of climate change and global warming, various alternatives are being considered as a potential replacement for fossil fuels. Despite often being overlooked, nuclear power offers many benefits as a low-carbon energy source. Being a thermal power plant, nuclear power can generate energy reliably without relying on weather without emitting greenhouse gases during its operation. Serialised construction can reduce the capital cost, which often touted as expensive. Due to the commitment to the Paris Protocol, Indonesia is obliged to achieve carbon neutrality in its energy generation, and nuclear power is a plausible option to replace fossil fuel generation. One of the questions regarding nuclear power deployment in Indonesia is the sustainability of the nuclear fuel, especially considering its domestic resources both uranium and thorium. This study estimates how long uranium and thorium resources in Indonesia will last when used to power the nuclear power plants with open and closed fuel cycles. Several reactor designs were considered. The calculation result shows that domestic nuclear fuel resources in Indonesia can be sustainable enough, provided that closed nuclear fuel cycle is deployed.
Co-Authors Andang Widiharto Miftasani, Fitria