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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Saga Octadamailah
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PENGARUH ROL DINGIN TERHADAP SIFAT MEKANIK MATERIAL AL 6061-T6 Saga Octadamailah; Dwi Marta Nurjaya; Supardjo; Ganisa Kurniati Suryaman
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 1 (2021): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.1.6339

Abstract

PENGARUH PROSES PENGEROLAN DINGIN TERHADAP SIFAT MEKANIK MATERIAL AL 6061-T6. Proses pembuatan pelat tutup dan pelat bingkai untuk pelat elemen bakar reaktor G.A. Siwabessy dilakukan dengan cara dirol dingin, sehingga dicapai ketebalan yang diinginkan. Pada penelitian sebelumnya, proses pengerolan dingin pada material AlMg2 menyebabkan perubahan sifat mekanik, dimana material menjadi lebih ulet dan kekuatan tariknya menurun. Pada bahan bakar densitas tinggi, material kelongsong Al 6061-T6 akan digunakan untuk menggantikan material kelongsong sebelumnya, yaitu AlMg2. Tujuan dari penelitian ini adalah untuk mengetahui perubahan sifat mekanik dari material Al 6061-T6 hasil pengerolan. Untuk melihat perubahan sifat mekanik yang terjadi, dilakukan uji tarik, pengamatan mikrostruktur dan struktur kristal. Hasil uji tarik menunjukkan bahwa kekuatan tarik, modulus elastis dan kekuatan luluh cenderung naik seiring dengan besarnya derajat reduksi ketebalan. Meskipun demikian, kekuatan luluh dari hasil pengujian cukup rendah. Rasio antara kekuatan luluh dan kekuatan tariknya hanya 0,7. Dari hasil pemindaian menggunakan difraksi sinar-X diketahui bahwa proses pengerolan dapat menyebabkan penghalusan ukuran kristalit. Kesimpulan dari penelitian ini secara umum adalah proses pengerolan dapat meningkatkan sifat mekanik material Al 6061-T6.
ANALISIS KRITIKALITAS PROSES HYDRIDING SERTA PENYIMPANAN PADUAN UMo DAN UZr SEBAGAI KANDIDAT BAHAN BAKAR REAKTOR RISET MENGGUNAKAN OPENMC Saga Octadamailah; Anissa Isnaini; Rohmad Sigit
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 29 No. 1 (2023): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2023.29.1.6976

Abstract

Current research on research reactor fuel is focused at increasing uranium density to produce higher neutron flux in order to increase radioisotope production as well as efficiency and accuracy in various material tests. Research and developments of nuclear fuel in Indonesia in order to increase uranium density is the development of UMo and UZr. One of the processes for making UMo and UZr powder is through a hydriding-dehydriding process which involves enriched uranium, and high pressure hydrogen gas. This combination presents the potential for criticality accidents that must be anticipated. Criticality calculations were carried out using OpenMC software, which is a nuclear physics simulation that uses the Monte Carlo method. In this simulation, two types of alloys are used, namely U7Mo and U6Zr. Simulations were carried out using 10,000 particles and 44 batches as parameter settings. From the simulation results, the keff value for the U7Mo and U6Zr alloy are 0.0297 and 0.0314, respectively. Both values are far below the critical value, indicating that the potential for criticality accidents is very low. In the storage simulation of hydriding products, there is the potential for criticality accidents if the storage bottles are placed close together without any distance. To anticipate this risk, each bottle must be given a safe distance and there needs to be a limit on the permitted mass of uranium per unit volume.
PENGARUH DENSITAS URANIUM TERHADAP UMUR BAHAN BAKAR NUKLIR DI DALAM REAKTOR RSG-GAS DITINJAU DARI ASPEK NEUTRONIK Saga Octadamailah; Supardjo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 2 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2017.23.2.3550

Abstract

Material Testing Reactor (MTR) is a research reactor with characteristics: small power, high thermal neutron flux and short life time fuel. Reaktor Serba Guna G.A. Siwabessy (RSG-GAS) located in Serpong is an MTR type reactor initially operated with dispersion fuel of U3O8/Al with uranium enrichment of 19.75 % 235U and uranium density of 2.96 gU/cm3. In an effort to increase the lifetime of nuclear fuel, BATAN has done research on high density uranium fuel starting from U3Si2/Al fule and continued with UMo based fuel in line with investigations performed by worldwide researchers in the field of research reactors. Fuel of U3Si2/Al with a density of 2.96 gU/cm3 has been successfully manufactured and utilized as fuel for RSG-GAS to substitute the U3O8/Al fuel. Post irradiation examination has also been done for U3Si2/Al with a density of 4.8 gU/cm3 up to a burn up of 60 %, while research on UMo with 7 gU/cm3 density has been progressing into mini plate fabrication. Research on high density fuel has been focused on fabrication process, while little has been done on lifetime calculation or utilization period. Therefore, this research has performed a calculation on nuclear fuel lifetime using a paired program of ORIGEN and MCNP. The calculation results show that an increase in uranium density will extend the lifetime of fuel exponentially. The longest lifetime is achieved by UMo type, which extends to 651 days, and this relates to a lifetime extension of 219 days if the RSG-GAS is operated with UMo fuel.
ANALISIS PENGARUH GEOMETRI FUEL ASSEMBLY TERHADAP KRITIKALITAS DAN DISTRIBUSI FLUKS NEUTRON DALAM TERAS REAKTOR RSG-GAS MENGGUNAKAN OPENMC Ibnu Fathan Rastri; Saga Octadamailah; Sukarman
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 30 No. 1 (2024): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2024.8681

Abstract

The G. A. Siwabessy Multi-Purpose Reactor (RSG–GAS) is included in the MTR type research reactor having a straight plate-shaped fuel element fueled by uranium silicide with a density of 2.96 gU/cm3. This research aims to analyze the influence of the geometry of the straight plate model fuel element on the criticality and distribution of neutron flux in the RSG–GAS reactor core. Monte Carlo simulations with OpenMC were carried out on five types of fuel elements namely from RSG–GAS, HANARO, WWR-SM, MARIA, and BRR, with mass U235 250 grams per fuel element. The research results show that the geometric shapes of different fuel elements influence the criticality value and flux distribution in the same core. The highest criticality value was obtained for the fuel element from HANARO followed by RSG-GAS and the lowest was obtained for the fuel element from WWR-SM. The flux distribution in the fuel elements from MARIA and BRR has a better flux distribution.
Co-Authors Anissa Isnaini Dwi Marta Nurjaya, Dwi Marta Ganisa Kurniati Suryaman Ibnu Fathan Rastri Rohmad Sigit Sukarman Supardjo