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Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code Ratna Dewi Syarifah; Nabil Nabhan MH; Zein Hanifah; Iklimatul Karomah; Ahmad Muzaki Mabruri
Jurnal Jaring SainTek Vol. 3 No. 1 (2021): April 2021
Publisher : Fakultas Teknik, Universitas Bhayangkara Jakarta Raya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.31599/jaring-saintek.v3i1.333

Analysis of fuel volume fraction with uranium caride fuel in Gas Cooled Fast Reactor (GFR) with SRAC Code is has been done. The calculation used SRAC Code (Standard Reactor Analysis Code) which is developed by JAEA (Japan Atomic Energy Agency), and the data libraries nuclear used JENDL 4.0. There are two calculation has been used, fuel pin cell calculation (PIJ Calculation) and core calculation (CITATION Calculation). In core calculation, the leakage is calculated so the calculation more precise. The CITATION calculation use two type of core configuration, i.e. homogeneous core configuration and heterogeneous core configuration. The power density value of two type core configuration is quite difference. It is better use heterogeneous core configuration than homogeneous core configuration, because the power density of heterogeneous core configuration is flatter than the other. From the analysis of fuel volume fraction, when the volume fraction is increase, the k-eff value is increase. And the optimum design after has been analysis for fuel volume fraction, that is the fuel volume fraction is 49% with a heterogeneous core configuration of three types of fuel percentages, for Fuel1 9%, Fuel2 12% and Fuel3 15%. This reactor is cylindrical, has a core diameter of 240 cm and a core height of 100 cm.

Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code Ratna Dewi Syarifah; Nabil Nabhan MH; Zein Hanifah; Iklimatul Karomah; Ahmad Muzaki Mabruri; Artoto Arkundato
Jurnal Jaring SainTek Vol. 3 No. 1 (2021): April 2021
Publisher : Fakultas Teknik, Universitas Bhayangkara Jakarta Raya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.31599/jaring-saintek.v3i1.333

Analysis of fuel volume fraction with uranium caride fuel in Gas Cooled Fast Reactor (GFR) with SRAC Code is has been done. The calculation used SRAC Code (Standard Reactor Analysis Code) which is developed by JAEA (Japan Atomic Energy Agency), and the data libraries nuclear used JENDL 4.0. There are two calculation has been used, fuel pin cell calculation (PIJ Calculation) and core calculation (CITATION Calculation). In core calculation, the leakage is calculated so the calculation more precise. The CITATION calculation use two type of core configuration, i.e. homogeneous core configuration and heterogeneous core configuration. The power density value of two type core configuration is quite difference. It is better use heterogeneous core configuration than homogeneous core configuration, because the power density of heterogeneous core configuration is flatter than the other. From the analysis of fuel volume fraction, when the volume fraction is increase, the k-eff value is increase. And the optimum design after has been analysis for fuel volume fraction, that is the fuel volume fraction is 49% with a heterogeneous core configuration of three types of fuel percentages, for Fuel1 9%, Fuel2 12% and Fuel3 15%. This reactor is cylindrical, has a core diameter of 240 cm and a core height of 100 cm.

Analysis of Tensile Strenght and Shear Modulus of GRE Pipe using Ansys Dita Puspita; Siti Lailatul Arofah; Elok Hidayah; Lutfi Rohman; Ratna Dewi Syarifah
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

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.

Study of Neptunium, Americium and Protactinium Addition for 300MWth GFR with Uranium Carbide Fuel Ratna Dewi Syarifah; Alvi Nur Sabrina
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

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.

TRASH CAN-COMPOSTER: ALAT PENCACAH SAMPAH ORGANIK UNTUK PENCACAH SAMPAH LIMBAH PERTANIAN Ratna Dewi Syarifah; Helda Wika Amini; Husnatun Nihayah; Nurul Ulya Luthfiyana
JMM (Jurnal Masyarakat Mandiri) Vol 6, No 3 (2022): Juni
Publisher : Universitas Muhammadiyah Mataram

Abstrak: Sampah merupakan segala sesuatu yang tidak lagi digunakan yang dihasilkan dari aktifitas manusia. Pengolahan sampah harus menjadi perhatian khusus agar tidak menimbulkan dampak negatif baik bagi masyarakat maupun lingkungan. Desa Pujer Baru Kecamatan Maesan Kabupaten Bondowoso belum memiliki fasulitas pembuangan sampah yang memadai. Masyarakat terbiasa membuang sampah di kebun, sungai hingga membakarnya dilingkungan sekitar. Tujuan kegiatan ini adalah untuk meningkatkan peran masyarakat dalam menangani sampah organik memalui sosialisasi dan diskusi pengolahan sampah, serta pelatihan dan pendampingan pengolahan sampah organik mengunakan mesin Trash Can-Composter sebagai komposter pencacah sampah organik untuk menghasilkan pupuk kompos. Kegiatan ini dilaksanakan di Desa Pujer Baru Kecamatan Maesan Kabupaten Bondowoso, Jawa Timur dengan peserta kegiatan merupakan ibu-ibu rumah tangga sejumlah 10 orang. Hasil dari pelatihan ini adalah adanya peningkatan pengetahuan masyarakat terkait pengolahan sampah, terbentuknya prototype tempat pengolahan sampah organik, mesin Trash Can-Composter, serta meningkatnya kemampuan manajemen pengolahan sampah organik melalui pembentukan kompos menggunakan mesin Trash Can-Composter.Abstract: Garbage is anything that is no longer used as a result of human activities. Waste processing must be a special concern so as not to cause negative impacts for both the community and the environment. Pujer Baru Village, Maesan District, Bondowoso Regency does not yet have adequate waste disposal facilities. People are used to throwing garbage in gardens, rivers and burning it in the surrounding environment. The purpose of this activity is to increase the role of the community in dealing with organic waste through socialization and discussion of waste management, as well as training and assistance in processing organic waste using the Trash Can-Composter machine as a composter to enumerate organic waste to produce compost. This activity was carried out in Pujer Baru Village, Maesan District, Bondowoso Regency, East Java with 10 housewives participating in the activity. The results of this training are an increase in community knowledge regarding waste processing, the formation of a prototype organic waste processing site, a Trash Can-Composter machine, and an increase in the ability to manage organic waste through the formation of compost using a Trash Can-Composter machine.

Rigid Procedure to Calculate the Melting Point of Metal Using the Solid-Liquid Phase (Coexistence) Method Artoto Arkundato; Wenny Maulina; Lutfi Rohman; Ratna Dewi Syarifah; Mohammad Ali Shafii
Jurnal Ilmu Fisika Vol 14 No 2 (2022): September 2022
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jif.14.2.132-140.2022

Melting point, particularly metal, is one of the important data for many applications. For developing new materials, adequate theories for melting point are very crucial. The determination of melting point using the popular phase-change curve method is very easy but usually overestimate. In current work, we determine the melting point of a pure metal (iron) using the method of solid-liquid phase coexistence. For this goal, molecular dynamics simulation was applied to obtain data of trajectories of atoms. Simulation (LAMMPS) and data analysis (OVITO) procedures are strictly applied to obtain the accurate melting point of iron based on the obtained trajectories data. For initial structure design of simulation, we used the ATOMSK program. The melting point of iron obtained using the phase change curve (PCC) method is about 2750 K < TPCC < 3250 K and using the coexistence phase (CP) method is TCP = 2325 K. A more accurate calculation needs to include defects factor in the simulated material and calculation. In this research we use the Morse potential to represent all of the atomic interaction among atoms of Fe material.

Validasi Kode OpenMC pada Reaktor Gas Berpendingin Helium Berbahan Bakar UC-PuC Iklimatul Karomah; Ratna Dewi Syarifah; Nuri Trianti; Artoto Arkundato; Lutfi Rohman; Wenny Maulina; Endhah Purwandari; Umar Sahiful Hidayat
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

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

ANALYSIS OF CORE CONFIGURATION FOR CONCEPTUAL GAS COOLED FAST REACTOR (GFR) USING OPENMC Iklimatul Karomah; Ahmad Muzaki Mabruri; Ratna Dewi Syarifah; Nuri Trianti
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 25, No 2 (2023): June 2023
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2023.6879

This study focused on a conceptual core configuration of Gas Cooled Fast Reactor (GFR), as part of a generation IV reactor. Uranium-plutonium carbide (UC-PuC) was used as reactor fuel and a Monte Carlo simulation method using OpenMC has been carried out. This study aims to find the composition of uranium-plutonium carbide fuel to use inside a fuel pin, making up a hexagonal prism fuel assembly arranged to form an entire core. A homogeneous and heterogeneous core configuration was considered in this study, while the plutonium percentage varied from 8%- 15%. For the homogenous core configuration, 10% was found as the optimum plutonium fraction with the value of %âˆ†k/k =1, which was then used as a reference to make up a heterogeneous core configuration. A heterogeneous core with 3 radial fuel regions of F1 using 9% Pu fraction, F2 10%, and F3 11% showed the most stable result for 5-year burn-up with a %âˆ†k/k of 0.7. The %âˆ†k/k value was decreased by 0.3 due to the fission reaction that occurred more evenly in all 3 fuel regions of heterogeneous configuration, reducing the core power peaking factor.Â Keywords: Core configuration, GFR, OpenMC, Reactivity, Fission reaction

Thermal Conductivity of Liquid Lead for the Fast Nuclear Reactor Coolant, Calculated by the Green-Kubo Method Using Molecular Dynamics Simulation Artoto Arkundato; Ratna Dewi Syarifah; Lutfi Rohman; Wenny Maulina; 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

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 Î» = 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.

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