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All Journal JOURNAL ONLINE OF PHYSICS Jurnal Fisika FLUX
Menik Ariani
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Earth & Planetary Sciences Education Materials Science & Nanotechnology Physics

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Desain Konseptual Reaktor Cepat Berpendingin Karbondioksida dan Berbahan Bakar Uranium Alam Dengan Daya 2400 MW Enda Susanty; Menik Ariani; Idha Royani; Zaki Su'ud; Fiber Monado
Jurnal Fisika FLUX Vol 17, No 2 (2020): Jurnal Fisika Flux: Jurnal Ilmiah Fisika FMIPA Universitas Lambung Mangkurat
Publisher : Lambung Mangkurat University Press

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1145.824 KB) | DOI: 10.20527/flux.v1i1.7184

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This paper presents the design concept of a carbon dioxide-cooled fast reactor.  This reactor utilize U-10%Zr as fuel and SS316 as cladding.  The strategy of modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy production) was applied for burnup in the core with power 2400 MW. The reactor core calculations were performed with a cylindrical geometry that is varied on the height and diameter of the core using a set of CITATION and PIJ modules on the SRAC (Standard Reactor Analysis Code) program. The ideal core size was obtained with a high of 350 cm, and a diameter of 240 cm with the resulting survey parameter are effective multiplication factor(keff), excess reactivity, radial and axial power distribution, and power peaking. The reactor core reaches a critical condition with keff 1.05 and excess reactivity 5.3% and radial power peaking 1.73. Optimization was done with power flattening, that is by dividing the core into two parts with a fuel fraction of 60% for the inner part with thick of 80 cm and fuel fraction of 65% for the outer part with thick of 40 cm, the results are 1.013, 1.3% and 1.5 for keff, excess reactivity, and radial power peaking, respectively.
ANALISIS NEUTRONIK KEKRITISAN TERAS REAKTOR NUSCALE BERBAHAN BAKAR DENGAN MENGGUNAKAN SOFTWARE OPENMC Canti Dwi Putri; Fiber Monado; Menik Ariani
JOURNAL ONLINE OF PHYSICS Vol. 8 No. 1 (2022): JOP (Journal Online of Physics) Vol 8 No 1
Publisher : Prodi Fisika FST UNJA

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22437/jop.v8i1.20812

Abstract

[Title: Neutronic Analysis of the criticality level of the nuscale reactor core with fuel using the openMC software] This study analyzed the design of the NuScale reactor, which aims to determine the level of criticality by modeling the shape of the cell pin, assembly, and core with nuclear fuel in the form of uranium dioxide, which will be varied by changing the percentage of uranium-235 content as much as 0% to 7% by using monte carlo methods in OpenMC program code. This study was conducted to obtain the design of nuclear reactors as well as the calculation of the effective multiplication factor, fission reaction rate, and neutron flux distribution for two years of the combustion process (Burn-up). The result of the calculation for the effective multiplication factor and reaction rate states that the greater the percentage of enrichment in uranium-235, the greater the value of the resulting in both parameters. While the distribution of neutron flux produces the most significant value in the middle region or center of the fuel and is seen from the average value produced, and the smallest value is at the edge of the cell. The analysis of this NuScale reactor can later be used as a reference in preparing a safe and efficient reactor core.
Co-Authors Canti Dwi Putri Enda Susanty Fiber Monado Idha Royani Zaki Su'ud