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All Journal Jurnal Teori dan Aplikasi Fisika Journal of Energy, Material, and Instrumentation Technology
Yanti Yulianti
University of Lampung
Astronomy Control & Systems Engineering Electrical & Electronics Engineering Energy Materials Science & Nanotechnology Physics

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PERHITUNGAN LAJU REAKSI NEUTRON DALAM REAKTOR SCWR (SUPERCRITICAL WATER REAKTOR) MODEL PERANGKAT (ASSEMBLY) HEKSAGONAL BERBAHAN BAKAR URANIUM Sharen Herya Reafinola; Yanti Yulianti; Syafriadi Syafriadi
Journal of Energy, Material, and Instrumentation Technology Vol 3 No 1 (2022): Journal of Energy, Material, and Instrumentation Technology
Publisher : Departement of Physics, Faculty of Mathematics and Natural Sciences, University of Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jemit.v3i1.84

Abstract

Calculation of the rate of fission and neutron capture reactions with a filter and without a filter has been carried out using a hexagonal geometry model using the REACT code SRAC program. This research uses uranium-235 and uranium-238 as fuel. Calculation results The rate of fission reaction in material 1 and material 3 using a filter and without a filter increases with the increase in the percentage value of U235 enrichment. The highest value for the neutron fission reaction rate of material 1 without a filter is found in the second mesh with 1% enrichment, which is 3.0747x10-2 reactions/cm3s. Meanwhile, the rate of neutron capture reaction using a filter increases with the increase in the percentage of U235 with 1% enrichment of the 5th mesh, with a value of 9.8627 x10-2 reactions/cm3s. Then the unfiltered neutron fission reaction rate on material 3 increased along with the increasing percentage in the 5th 1% enrichment mesh, which was 9.4778 x10-2 reactions/cm3s. This is due to the increasing percentage of U235 enrichment in the fuel pin. While the rate of capture reaction using a filter on material 1 with a percentage of 1% of the second mesh has the highest value compared to the filter, which is 9.8181 x10-2 reactions/cm3s.
Perhitungan Burn Up Model Assembly Heksagonal pada Reaktor SCWR Menggunakan Bahan Bakarr Thorium Mey Puji Astuti; Yanti Yulianti; Posman Manurung; Simon Sembiring
Journal of Energy, Material, and Instrumentation Technology Vol 3 No 1 (2022): Journal of Energy, Material, and Instrumentation Technology
Publisher : Departement of Physics, Faculty of Mathematics and Natural Sciences, University of Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jemit.v3i1.85

Abstract

The research about the calculation of burn-up model of the hexagonal assembly in SCWR reactor using thorium as fuel materials has been done. This research uses thorium-232 and uranium-233 as fuel materials. Calculations were performed using the ASMBURN code in the SRAC program, by determining fuel enrichment, cell radius, analyzing atomic density after burn up, increasing burn up level, and change of linear heat. The calculation results obtained show the value of efficient fuel enrichment at 4% enrichment, with 0.3902 cm of fuel cell radius, 0.4508 cm of cladding, and 0.5586 cm of moderator. The atomic density of Th232 decreased for each burn-up period meanwhile, the atomic density of U233, U235, and Pu239 increased. The keff value will decrease along with the addition of burn-up and greater change of linear heat.
Studi Pengaruh Ukuran Pebble bed Terhadap Termal Hidrolik Pada Thorium Molten Salt Reactor Solid Fuel (TMSR-SF) Menggunakan COMSOL Multiphysics I Gusti Ayu Putu Dwi Ekasari; Yanti Yulianti; Duwi Hariyanto; Gurum Ahmad Pauzi
Jurnal Teori dan Aplikasi Fisika Vol. 14 No. 02 (2026): Jurnal Teori dan Aplikasi Fisika
Publisher : Department of Physics, Faculty of Mathematics and Natural Sciences, University of Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v14i02.484

Abstract

Abstract. The development of nuclear energy, particularly in the Thorium Molten Salt Reactor Solid Fuel (TMSR-SF) requires a deep understanding of thermal-hydraulic characteristics, including temperature, flow velocity, and pressure within the reactor core. This research aims to analyze the influence of pebble bed diameter on temperature and pressure, as well as to examine the impact of initial fluid flow conditions on fluid velocity within the TMSR-SF reactor core. Simulations were conducted by the Heat Transfer in Fluids and Laminar Flow modules in the COMSOL Multiphysics application. The simulation results show that the highest temperature difference percentage between the 6 cm and 9 cm pebble beds is 0.7%, while between the 6 cm and 12 cm pebble beds, it is 1.7%. Percentage the highest pressure drop over time was observed in the 6 cm pebble bed at 1.6%, followed by the 9 cm pebble bed at 1.4%, and the 12 cm pebble bed at 1.5%. Additionally, the percentage difference off the initial fluid flow rate decreasing was recorded at 0.09% between the 6 cm and 9 cm pebble beds and 0.26% between the 9 cm and 12 cm pebble beds. The 6 cm pebble bed diameter provides more optimal thermal-hydraulic performance, particularly in terms of temperature stability and fluid flow consistency, which are crucial for the efficiency and safety of TMSR-SF reactor operation Keywords: COMSOL Multiphysics, TMSR-SF, thermal hydraulics, pebble bed, diameter variations
Co-Authors Duwi Hariyanto Gurum Ahmad Pauzi I Gusti Ayu Putu Dwi Ekasari Mey Puji Astuti Posman Manurung Sharen Herya Reafinola Simon Sembiring Syafriadi Syafriadi