Article Per Year (5 Year)
p-Index From 2020 - 2025
1.235
P-Index
This Author published in this journals
All Journal Jurnal Penelitian Fisika dan Aplikasinya (JPFA) Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Jurnal Fisika Unand Jurnal Elemen Computational and Experimental Research in Materials and Renewable Energy (CERiMRE)
Topan Setiadipura, Topan
Unknown Affiliation
Astronomy Automotive Engineering Chemical Engineering, Chemistry & Bioengineering Computer Science & IT Control & Systems Engineering Earth & Planetary Sciences Education Electrical & Electronics Engineering Energy Engineering Materials Science & Nanotechnology Physics

Published : 8 Documents Claim Missing Document
Claim Missing Document
Check
Articles

Found 8 Documents
Search

 1 
SIMULASI MCNP5 DALAM EKSPERIMEN KRITIKALITAS LARUTAN PLUTONIUM–URANIUM NITRAT DENGAN REFLEKTOR AIR DAN POLYETHYLENE Andiwijayakusuma, Dinan; Setiadipura, Topan; Zuhair, Z
Jurnal Penelitian Fisika dan Aplikasinya (JPFA) Vol 1, No 2 (2011)
Publisher : Universitas Negeri Surabaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26740/jpfa.v1n2.p1-7

Abstract

Banyak perangkat kritik dibangun untuk memenuhi kebutuhan studi fenomena kecelakaan kritikalitas pada larutan fisil di fasilitas daur bahan bakar nuklir. Salah satu diantaranya adalah perangkat kritik SCAMP. Di perangkat ini dikerjakan eksperimen kritikalitas menggunakan bejana silindris stainless steel berisi larutan plutonium- uranium nitrat (Pu+U nitrat). Sebanyak 7 eksperimen didemonstrasikan dengan reflektor air di semua sisi permukaan bejana larutan kecuali di bagian atas bejana. Makalah ini membahas simulasi transport Monte Carlo MCNP5 dalam eksperimen kritikalitas larutan Pu+U nitrat dengan reflektor air dan polyethylene. Simulasi MCNP5 dengan pustaka ENDF/B-VI memberikan hasil yang paling dekat dengan data eksperimen terutama pada kasus A untuk varian geometri 4. Dibandingkan pustaka ENDF/B-V, perhitungan kritikalitas dengan pustaka ENDF/B-VI memberikan hasil lebih dekat dengan perhitungan MONK dimana bias perhitungannya < 0,44%, khususnya pada kasus A namun pada kasus B dan C simulasi MCNP5 dengan pustaka ENDF/B-V memberikan hasil dengan kecenderungan lebih baik dibandingkan pustaka ENDF/B-VI dengan bias perhitungan < 2,67% dan < 1,13%. Secara keseluruhan dapat disimpulkan bahwa MCNP5 telah menunjukkan reliabilitasnya dalam simulasi kritikalitas larutan Pu+U nitrat.
DESAIN OPTIMAL TERAS SMALL MODULAR MOLTEN SALT REACTOR (SM-MSR) SEBAGAI SISTROPULSI KAPAL PERANG EM P Prabudi, Cahyo Ridho; Aritonang, Sovian; Setiadipura, Topan
ELEMEN : JURNAL TEKNIK MESIN Vol. 10 No. 1 (2023)
Publisher : POLITALA PRESS

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.34128/je.v10i1.238

Abstract

Utilizing a nuclear propulsion system as a source of propulsion is one method for extending the durability of warships. Compared to using natural oil, using nuclear energy as a propulsion system offers a high effectiveness value. The Molten Salt Reactor illustrates a reactor design that can be utilized on warships (MSR). The current MSR is still quite big. Therefore in this research, an optimal design of the Small Modular Molten Salt Reactor (SM-MSR) core will be adapted to the surface area of ​​a warship. From the simulation and optimization carried out with the MCNP software, the parameter used as a reference is criticality. The optimal fuel material composition is 1% Li and 2% U-235, with an optimal design geometry having a cell core pin radius of 0.8 cm, a pin cell blanket radius of 2.6 cm, and a core height of 160 cm. The initial design of the SM-MSR in this study had a negative coefficient of void reactivity.
Molecular Docking Study: Identification of Potential Inhibitors in Lavandula Angustifolia Essential Oil Against the Main Protease of Sars-Cov-2 Sahiroh, Samakhatus; Sulisti, Wahyu; Sunnardianto, Gagus Ketut; Setiadipura, Topan; Kharomah, Iklimatul
Computational And Experimental Research In Materials And Renewable Energy Vol 6 No 1 (2023): 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.v6i1.43190

Abstract

SARS-CoV-2, also known as, Covid-19 is an almost globally endemic disease that has infected hundreds of millions of people and caused ongoing deaths. Researchers are still trying to search for effective drugs against Covid-19. Currently, with the development of science and technology, the process of drug discovery through simulated environments is becoming increasingly accurate and yielding rapid results. The protease crystal structure of Covid-19 plays a crucial role in viral replication and represents promising primary targets for antiviral drug discovery and therapy. Lavender and N3 compound ligands were used as test ligands. A total of 9 lavender ligand compounds were subjected to testing using the molecular docking method. Molecular docking aims to achieve the optimal conformation of both the protein and ligand, as well as the relative orientation between them. The analysis conducted during molecular docking includes the determination of the inhibition constant and the study of interactions between the protein and ligand.Keywords: Covid-19, docking, N3, ligand
Insider Intervention Model in the Sabotage Attack Scenario of a Nuclear Reactor Facility Andiwijayakusuma, Dinan; Asmoro, Teguh; Mardhi, Alim; Setiadipura, Topan
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 26, No 1 (2024): February 2024
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2024.7008

Abstract

The Physical Protection System (PPS) at nuclear facilities aims to prevent intrusions into nuclear facilities that cause sabotage attacks or illegal theft of nuclear material. The outsider, the insider or a collaboration of both can carry out this intrusive action. In this study, we modelled the insider collaborating with the outsider to carry out nuclear facility attacks using sabotage attack scenarios. The modelling takes the form of insider intervention on two parameters protection elements:the time delay () and the probability of detection (). Insider intervention in delay protection elements might have fatal consequences and drastically reduce the effectiveness of PPS performance. Therefore, PPS designers need to pay more attention to the delay element to anticipate the negative impact of insider intervention on the effectiveness of the PPS.
The Study of Multiaxial Loading and Damage to the Structure and Materials in the PWR Steam Generator of Nuclear Reactor Subhan, Muhammad; Priyana Soemardi, Tresna; Setiadipura, Topan; Yogatama Sulistyo, Farisy; Subiyah, Hana
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.2023.6963

Abstract

In Pressurized Water Reactor (PWR) Nuclear Power Plants (NPPs), the steam generator is crucial for transferring heat from the primary to secondary cooling systems, vital for steam production to drive turbines, and central to nuclear power safety. This study explores recent research on multi-axial loading, structural integrity, and material durability in PWR steam generators, shedding light on key factors affecting these systems. Common corrosion-related degradation in steam generators often arises from design, material, and water chemistry factors. However, the shift to All Volatile Treatment (AVT), the development of advanced material alloys, and enhanced water quality control in primary and secondary systems have significantly reduced instances of steam generator degradation. These findings promise to enhance the reliability and safety of steam generators in future nuclear applications. 
DESAIN OPTIMAL TERAS SMALL MODULAR MOLTEN SALT REACTOR (SM-MSR) SEBAGAI SISTROPULSI KAPAL PERANG EM P Prabudi, Cahyo Ridho; Aritonang, Sovian; Setiadipura, Topan
ELEMEN : JURNAL TEKNIK MESIN Vol. 10 No. 1 (2023)
Publisher : POLITALA PRESS

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.34128/je.v10i1.238

Abstract

Utilizing a nuclear propulsion system as a source of propulsion is one method for extending the durability of warships. Compared to using natural oil, using nuclear energy as a propulsion system offers a high effectiveness value. The Molten Salt Reactor illustrates a reactor design that can be utilized on warships (MSR). The current MSR is still quite big. Therefore in this research, an optimal design of the Small Modular Molten Salt Reactor (SM-MSR) core will be adapted to the surface area of ​​a warship. From the simulation and optimization carried out with the MCNP software, the parameter used as a reference is criticality. The optimal fuel material composition is 1% Li and 2% U-235, with an optimal design geometry having a cell core pin radius of 0.8 cm, a pin cell blanket radius of 2.6 cm, and a core height of 160 cm. The initial design of the SM-MSR in this study had a negative coefficient of void reactivity.
Optimisasi Ukuran Teras High Temperature Gass-cooled Reactor (HTGR) dengan Daya 30 MWt Tipe Pebble Bed Berbasis Bahan Bakar Uranium Armanita, Desi; Fitriyani, Dian; Setiadipura, Topan
Jurnal Fisika Unand Vol 9 No 1 (2020)
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jfu.9.1.100-109.2020

Abstract

Telah dilakukan optimasi ukuran teras Reaktor daya Eksperimental (RDE). Optimasi ini bertujuan untuk memperoleh ukuran teras yang optimal untuk RDE 30 MWt berdasarkan aspek neutronik antara lain discharge burn up, fuel residence time dan distribusi daya dan aspek keselamatan. Pada tahap awal dilakukan optimasi pass bahan bakar. Pass bahan bakar menyatakan jumlah sirkulasi bahan bakar ke teras reaktor dan parameter optimasi pass adalah nilai power peaking factor mendekati 1, discharge burn up tinggi serta memiliki temperatur puncak bahan bakar setelah DLOFC rendah. Berdasarkan parameter tersebut didapatkan pass optimal adalah 5 pass. Variasi ukuran teras ditentukan dengan dua cara, yaitu variasi ukuran teras pada volume tetap dan variasi tinggi teras pada diameter tetap. Tahap selanjutnya, terhadap ukuran teras yang optimal, dilakukan optimasi fraksi enrichment dan heavy metal loading bahan bakar. Dari hasil perhitungan diperoleh bahwa pada volume tetap (5 m3) parameter-parameter neutronik bernilai optimal jika ukuran diameter teras 1,5 m dan tinggi 2,83 m, sedangkan pada diameter teras tetap (1,8 m) parameter-parameter neutronik optimal pada ukuran tinggi teras 3,931 m.  Pada kedua ukuran teras ini aspek keselamatan, discharge burn up dan fuel residence time optimal pada enrichment 17% dan heavy metal loading 6 grU/pebble. Core size optimization of Experimental Power Reactor (EPR) has been done. This optimization aims to obtain the optimal core size for the RDE 30 MWt based on the neutronik aspect among other discharge burn ups, fuel residence time, power distribution and safety aspect. In the early stages the fuel pass optimization is done. The fuel pass is the amount of fuel circulation to the reactor core and the pass optimization parameter is the value of power peaking factor approaching 1, high discharge burnup as well as having a fuel peak temperature after DLOFC is low. According to the parameters, the optimal pass is 5 passes. The variation in the size of the core is determined in two ways, which is the core size variation on fixed volumes and a high variation of the core at fixed diameter. The next stage, against the optimal core size, carried out the optimization of the fraction of enrichment and heavy metal loading fuel.  From the results of the calculations obtained that on a fixed volume (5 m3) neutronik parameters are optimal if the size of the core diameter is 1.5 m and height 2.83 m, while on the fixed diameter of the ratio (1.8 m) The optimal neutronik parameters of on the size Height of core 3.931 m.  On both of these core sizes are safety aspects, discharge burn up and fuel residence time is optimal on the enrichment of 17% and heavy metal loading 6 grU/pebble.
Analisis Neutronik dan Temperatur Bahan Bakar Setelah Depressurized Loss of Forced Cooled (DLOFC) pada Pebble Bed Reactor (PBR) dengan Upgrade Daya Rosyidah, Amalia; Fitriyani, Dian; Setiadipura, Topan
Jurnal Fisika Unand Vol 9 No 2 (2020)
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jfu.9.2.231-237.2020

Abstract

Pada penelitian ini dilakukan analisis neutronik dan temperatur bahan bakar setelah DLOFC pada Pebble Bed Reactor (PBR) dengan upgrade daya. Reaktor acuan yang digunakan dalam penelitian ini yaitu HTR-PM. Penelitian ini bertujuan untuk memperoleh desain reaktor dengan daya 300 MWt. Perhitungan dalam penelitian ini menggunakan software PEBBED6 code. Pada tahap awal dilakukan upgrade daya pada desain default HTR-PM. Parameter neutronik yang diperhatikan dalam penelitian ini yaitu nilai burnup yang tinggi dan temperatur puncak bahan bakar setelah DLOFC tidak melebihi 1620 oC. Berdasarkan capaian kedua parameter tersebut, daya pada desain default HTR-PM hanya dapat ditingkatkan hingga 260 MWt. Selanjutnya perhitungan pada daya yang di-upgrade disertai dengan pengaturan pada enrichment dan HM loading. Dari hasil pengamatan disimpulkan bahwa dengan enrichment dan HM loading yang tinggi maka semakin tinggi densitas bahan fisil sehingga dapat memperbesar nilai burnup dan juga temperatur puncak setelah DLOFC. Selanjutnya dilakukan optimasi ketinggian dan diameter teras reaktor dengan volume teras default (77,44 m3). Diameter teras yang diperkecil dapat menghantarkan panas hasil reaksi fisi keluar teras lebih maksimal. Kemudian dilakukan pengaturan enrichment dan HM loading bahan bakar kembali untuk mendapatkan daya maksimal. Desain optimal pada penelitian ini diperoleh untuk daya 300 MWt dengan HM loading 6 gU/pebble, enrichment 8,5% dan tinggi teras 14,64 m yang dapat menghasilkan nilai burnup 77,11 MWd/Kg.HM. In this research neutron and fuel temperature analysis is done after DLOFC on the Pebble Bed Reactor (PBR) with a power upgrade. The reference reactor used in this study is HTR-PM. This study aims to obtain a reactor design with 300 MWt of power. The calculation in this study use the PEBBED6 code software. In the initial stage, a power upgrade is performed on the default HTR-PM design. The neutronic parameters considered in this study are high burnup values and peak temperature after DLOFC do not exceeding 1620 oC. Based on the achievement of the two parameters, the power in the default HTR-PM design can only be increased up to 260 MWt. Furthermore, calculation on the upgraded power are accompanied by setting on the enrichment and HM loading. The next step is optimizing the height and diameter of the reactor core by maintaining the default core volume (77.44 m3). The reduced diameter of the terrace can deliver maximum heat from the fission reaction outside the terrace. Then the enrichment and HM loading of the fuel are regulated to get maximum power. The optimal design in this study was obtained for 300 MWt power with HM loading of 6 gU/pebble, 8.5% enrichment and a terrace height of 14.64 m which can produce a burnup value of 77.11 MWd/Kg.HM.
Co-Authors Alim Mardhi, Alim Aritonang, Sovian Armanita, Desi Asmoro, Teguh Cahyo Ridho Prabudi Dian Fitriyani Dinan Andiwijayakusuma Kharomah, Iklimatul Muhammad Subhan Priyana Soemardi, Tresna Rosyidah, Amalia Sahiroh, Samakhatus Subiyah, Hana Sulisti, Wahyu Sunnardianto, Gagus Ketut Yogatama Sulistyo, Farisy Zuhair, Z