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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Science and Technology Indonesia Jurnal Penelitian Pendidikan IPA (JPPIPA) JMM (Jurnal Masyarakat Mandiri) Jurnal Ilmu Fisika Indonesian Physical Review Jurnal Jaring SainTek Computational and Experimental Research in Materials and Renewable Energy (CERiMRE) Dedikasi: Jurnal Pengabdian kepada Masyarakat Journal of Energy, Material, and Instrumentation Technology JIFP (Jurnal Ilmu Fisika dan Pembelajarannya) Newton-Maxwell Journal of Physics Sewagati
Syarifah, Ratna Dewi
Department Of Physics, Faculty Of Mathematics And Natural Sciences, Universitas Jember
Agriculture, Biological Sciences & Forestry Arts Humanities Astronomy Biochemistry, Genetics & Molecular Biology Chemical Engineering, Chemistry & Bioengineering Chemistry Computer Science & IT Control & Systems Engineering Earth & Planetary Sciences Education Electrical & Electronics Engineering Energy Engineering Environmental Science Industrial & Manufacturing Engineering Languange, Linguistic, Communication & Media Materials Science & Nanotechnology Mechanical Engineering Physics Public Health Social Sciences Other

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Study of Neptunium, Americium and Protactinium Addition for 300MWth GFR with Uranium Carbide Fuel Syarifah, Ratna Dewi; Sabrina, Alvi Nur
Computational And Experimental Research In Materials And Renewable Energy Vol 2 No 2 (2019): November
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.v2i2.27368

Abstract

A study of Neptunium, Americium, and Protactinium addition for GFR 300MWth with Uranium Carbide fuel has been performed. The purpose of this study was to determine the characteristics of addition Neptunium, Americium, and Protactinium in a 300MWth Gas-Cooled Fast Reactor. Neutronics calculation was design by using Standard Reactor Analysis Code (SRAC) version 2006 with data nuclides from JENDL-4.0. Neutronics calculations were initiated by calculating the fuel cell calculation (PIJ calculation) and continued with the reactor core calculation (CITATION calculation). The reactor core calculation used two-reactor core configurations, namely the homogeneous core configuration and heterogeneous core configuration. The Neptunium, Americium, and Protactinium additions were performed after obtaining the optimal condition from heterogeneous core configuration. The addition of Neptunium and Americium which are Spent Nuclear Fuel (SNF) from LWR fuels, aims to reduce the amount of Neptunium and Americium in the world and also to reduce the effective multiplication factor (k-eff) value from the reactor. The results obtained that the addition of Neptunium and Americium causes the k-eff value was decreased at the beginning of burn-up time, but increase at the end of burn-up time. It was because Neptunium and Americium absorb neutrons at the beginning of burn-up time and turns into fissile material at the end of burn-up time. The addition of protactinium in the reactor causes the k-eff value to be decreased both at the beginning of the burn-up time and at the end of the burn-up time. It happens because Protactinium absorbs neutrons both at the beginning of the burn-up time and at the end of the burn-up time. Therefore protactinium is often called a burnable poison.
Analysis of Tensile Strenght and Shear Modulus of GRE Pipe using Ansys Puspita, Dita; Arofah, Siti Lailatul; Hidayah, Elok; Rohman, Lutfi; Syarifah, Ratna Dewi
Computational And Experimental Research In Materials And Renewable Energy Vol 1 No 1 (2018): November
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.v1i1.19544

Abstract

Composite materials (GRE pipe) had been applied in various industries. These kind application are based on the advantages of composite properties, that are lightweight, high corrosion resistance and low cost. In order to make a lightweight and strong materials, some materials that light and stiff had been widely used, lie fiber glass, epoxy and the other. These materials (fiber glass and epoxy) are synthetic and non-biodegradable, but give some advantages in composite to make composite more stiff, light and strong. Mechanical properties of fiber glass composites had been doing based on theory through modeling. Theoretical results obtained showed that maximum stress and shear modulus value of GRE pipe are less than each components (glass fiber and epoxy resin). Each value of maximum stress and shear modulus are 584,57 MPa and 46,15 MPa.
Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation Mabruri, Ahmad Muzaki; Syarifah, Ratna Dewi; Aji, Indarta Kuncoro; Arkundato, Artoto; Trianti, Nuri
Jurnal Ilmu Fisika Vol 16 No 2 (2024): September 2024
Publisher : Jurusan Fisika FMIPA Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jif.16.2.107-117.2024

Abstract

Validation of Low-Cycle and Low-Particle OpenMC Simulation Codes for Neutronics Calculations has been conducted. This study validates OpenMC, an evolving open-source neutron analysis code. Validation of Low-Cycle and Low-Particle Codes is crucial as it allows for effective calculations with minimal computational resources. Determining the convergence point of cycles and minimum particles in low-cycle and low-particle calculations enables maintaining calculation accuracy, thus providing sufficiently accurate results. This study demonstrates that a minimum of 15,000 particles, 100 cycles (30 inactive, 70 active), is required for low-cycle simulations. A comparison of k-eff calculation results with the SRAC code for MSR FUJI-12 at 7 burnup points (0-27 MWd/ton) yields a maximum error of 0.7%. These results validate the effectiveness of OpenMC in achieving accurate neutronic calculations with limited computational resources
Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation Mabruri, Ahmad Muzaki; Syarifah, Ratna Dewi; Aji, Indarta Kuncoro; Arkundato, Artoto; Trianti, Nuri
Jurnal Ilmu Fisika Vol 16 No 2 (2024): September 2024
Publisher : Jurusan Fisika FMIPA Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jif.16.2.107-117.2024

Abstract

Validation of Low-Cycle and Low-Particle OpenMC Simulation Codes for Neutronics Calculations has been conducted. This study validates OpenMC, an evolving open-source neutron analysis code. Validation of Low-Cycle and Low-Particle Codes is crucial as it allows for effective calculations with minimal computational resources. Determining the convergence point of cycles and minimum particles in low-cycle and low-particle calculations enables maintaining calculation accuracy, thus providing sufficiently accurate results. This study demonstrates that a minimum of 15,000 particles, 100 cycles (30 inactive, 70 active), is required for low-cycle simulations. A comparison of k-eff calculation results with the SRAC code for MSR FUJI-12 at 7 burnup points (0-27 MWd/ton) yields a maximum error of 0.7%. These results validate the effectiveness of OpenMC in achieving accurate neutronic calculations with limited computational resources
OPTIMIZING THE CARBONIZATION TEMPERATURE OF WATER HYACINTH BIOCHAR BY PROXIMATE ANALYSIS USING RESPONSE SURFACE METHODOLOGY Maulina, Wenny; Habibah, Putri Sifa; Arkundato, Artoto; Syarifah, Ratna Dewi; Sulistiyo, Yudi Aris; Sukmawati, Nissa
Indonesian Physical Review Vol. 8 No. 1 (2025)
Publisher : Universitas Mataram

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.29303/ipr.v8i1.405

Abstract

Water hyacinth is a locally available biomass with the potential to be converted into biochar, serving as a renewable energy source. In this report, response surface methodology (RSM) was employed to optimize the carbonization temperature during the preparation of water hyacinth biochar. Water hyacinth was carbonized in a furnace at varied temperatures (400 °C, 500 °C, 600 °C) for 90 minutes. Characterization of the biochar derived from water hyacinth by proximate analysis was determined, including moisture content, ash content, volatile matter, fixed carbon, and calorific value. The results of the biochar before optimization indicated that moisture content and volatile matter decreased with increasing carbonization temperature, while ash content, fixed carbon, and calorific value increased. After optimization, the proximate analysis of the biochar was determined, with the optimal carbonization temperature found to be 533.54 °C. At this temperature, the optimal moisture content was 6.50%, ash content was 25.53%, volatile matter was 24.80%, and fixed carbon was 43,16%. These findings demonstrate the feasibility of using RSM to optimize the preparation conditions of water hyacinth biochar.
Validasi Kode OpenMC pada Reaktor Gas Berpendingin Helium Berbahan Bakar UC-PuC Karomah, Iklimatul; Syarifah, Ratna Dewi; Trianti, Nuri; Arkundato, Artoto; Rohman, Lutfi; Maulina, Wenny; Purwandari, Endhah; Hidayat, Umar Sahiful
Newton-Maxwell Journal of Physics Vol. 4 No. 1: April 2023
Publisher : UNIB Press

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.33369/nmj.v4i1.26998

Abstract

Validasi perhitungan kekritisan pada Gas Cooled Fast Reactor (GFR) menggunakan kode OpenMC dan SRAC telah dilakukan. OpenMC merupakan kode analisis neutronik yang bersifat open source dan probabilistik yang sedang dikembangkan oleh MIT hingga sekarang. Validasi kode OpenMC perlu dilakukan untuk menunjukkan hasil validitas perhitungan OpenMC dibandingkan dengan kode lainnya. OpenMC yang bersifat probabilistik, mensimulasikan random sampling partikel yang berjumlah besar. Hal terseut bertujuan untuk menunjukkan akurasi perhitungan OpenMC dengan menggunakan partikel yang berjumlah kecil. Validasi dilakukan dengan melihat selisih perhitungan nilai  dari kode OpenMC dan SRAC. Nilai konvergensi yang dihasilkan dari kode OpenMC dan SRAC dikatakan tervalidasi dengan memiliki nilai error <1%. Pada penelitian ini menggunakan 50.000 partikel dengan total pengulangan 100 batch aktif dan 30 batch tidak aktif yang disimulasikan. Hasil perbandingan menunjukkan bahwa OpenMC memiliki error maksimal 0,06% terhadap hasil perhitungan kode SRAC
Thermal Conductivity of Liquid Lead for the Fast Nuclear Reactor Coolant, Calculated by the Green-Kubo Method Using Molecular Dynamics Simulation Arkundato, Artoto; Syarifah, Ratna Dewi; Rohman, Lutfi; Maulina, Wenny; Widiasih
Jurnal Penelitian Pendidikan IPA Vol 9 No 12 (2023): December
Publisher : Postgraduate, University of Mataram

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.29303/jppipa.v9i12.6102

Abstract

Comprehensive information about nuclear reactor coolant materials for application in heat-transfer systems is very important. One important physical property that needs to be known is the thermal conductivity. The goal of this work is to predict the thermal conductivity value of the liquid lead, which is one of the important candidates for cooling materials for Gen-IV fast nuclear reactor designs. The thermal conductivity of liquid lead in this study was predicted using the Green-Kubo scheme and the molecular dynamics (MD) computational method to collect the simulation data. The MD simulation was done in the NVT ensemble, using the Lennard-Jones interaction potential. We observe the thermal conductivity of the liquid lead can be studied based on the diffusion physical process. The thermal conductivity of the liquid lead obtained from this research is λ = 0.0113T + 8.8539 [W/mK]. As a conclusion, this result is very suitable, compared with the available experimental data, then the Green-Kubo method can be used to calculate the thermal conductivity of liquid metal as lead.
Co-Authors Ahmad Muzaki Mabruri Ahmad Muzaki Mabruri Arofah, Siti Lailatul Artoto Arkundato Dita Puspita, Dita Endhah Purwandari Fajri Prasetya Habibah, Putri Sifa Helda Wika Amini Helda Wika Amini Hidayah, Elok Hidayat, Umar Sahiful Husnatun Nihayah Iklimatul Karomah Iklimatul Karomah Indarta Kuncoro Aji Karomah, Iklimatul Lutfi Rohman Ma'rifah, Binti Ni'matul Mabruri, Ahmad Muzaki Maulana, Muhammad Rizqi Meirita Dwi Afriani Mohammad Ali Shafii Nabil Nabhan MH Nabil Nabhan MH Nuri Trianti Nurul Ulya Luthfiyana Prasetya, Fajri Prasetyani, Tiana Febrianti Eka Sabrina, Alvi Nur Setiawan, Dimas Arif Shofa, Ghaitsa Zhahira Sholihah, Athaya Farras Sukmawati, Nissa Syaifullah, Rangga Yudha Trianti, Nuri Wenny Maulina Wenny Maulina, Wenny Widiasih Wika Amini, Helda Yudi Aris Sulistiyo, Yudi Aris Zein Hanifah Zein Hanifah