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All Journal Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Rohmad Sigit
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Materials Science & Nanotechnology

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ANALISIS KETIDAKPASTIAN PENGUKURAN KEKUATAN TARIK DAN ELONGASI SPESIMEN SS304 BERBENTUK RING Sri Ismarwanti; Jan Setiawan; Maman Kartaman Ajiriyanto; Rohmad Sigit
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 27, No 3 (2021): Oktober, 2021
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.3.6567

Abstract

ANALISIS KETIDAKPASTIAN PENGUKURAN KEKUATAN TARIK DAN ELONGASI SPESIMEN SS304 BERBENTUK RING. Ketidakpastian adalah tolok ukur dari kehandalan suatu pengukuran. Salah satu pendekatan analisa ketidakpastian yang banyak digunakan adalah dengan menggunakan Guide to the expression of uncertainty in measurement (GUM). Langkah-langkah untuk menganalisa ketidakpastian dari suatu pengukuran telah dijelaskan secara rinci oleh pendekatan GUM. Analisa ketidakpastian dilakukan pada pengujian tarik untuk mengetahui ketertelusuran data yang diperoleh. Pengujian tarik menghasilkan data berupa kekuatan tarik dan elongasi dari material uji.  Kekuatan tarik adalah besaran yang melibatkan besaran gaya dan panjang. Elongasi adalah penambahan panjang saat dilakukan penarikan. Kekuatan tarik pada sampel berbentuk ring akan dipengaruhi oleh luas penampang pada kedua belah sisi ring ketika diberikan tegangan tarik. Sehingga untuk menentukan ketidakpastian pengujian tarik akan memerlukan analisa terhadap penyumbang ketidakpastian. Makalah ini memberikan penjelasan bagaimana cara untuk menganalisa ketidakpastian pengukuran kekuatan tarik dan elongasi pada sampel berbentuk ring. Selain itu juga akan diperoleh nilai ketidakpastian pengukuran kekuatan tarik dan elongasi SS304 berbentuk ring. Dari pengujian yang dilakukan dapat diketahui bahwa kekuatan tarik ring SS304 rata-rata adalah 631,070 ± 26,976 Nmm-2 dengan ketidakpastian diperluas sebesar 50,451 Nmm-2 pada tingkat kepercayaan 95%. Selain itu pada tingkat kepercayaan yang sama diperoleh hasil elongasi ring SS304 rata-rata 18,681% ± 2,425% dengan ketidakpastian diperluas sebesar 2,867%. Keberulangan data atau repeatability menjadi penyumbang terbesar terhadap ketidakpastian pengukuran kekuatan tarik dan elongasi ring SS304.Kata kunci: Ketidakpastian, GUM, kekuatan tarik, elongasi, ring SS304.
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.
IMAGE ENHANCEMENT CITRA DIGITAL SHORT PIN PWR FUEL BERISI PELET UO2 ALAM PASCA UJI RADIOGRAFI SINAR-X MENGGUNAKAN PROGRAM IMAGEJ Refa Artika; Rohmad Sigit; Maman Kartaman Ajiriyanto; Tri Yulianto
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 1 (2022): 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.2022.28.1.6617

Abstract

Non-destructive test using digital X-ray radiography is one of the important series in performance evaluation of nuclear materials and fuels. Image enhancement or image quality improvement is needed for further analysis of digital X-ray radiography images which tend to have lower resolution. Image enhancement process on digital x-ray radiographic images needs to be carried out to provide images that are easier to interpret so that the resulting data can be used as a basis for evaluating performance after irradiation. The tests were performed at a distance of 40 cm against the detector at voltage and current of 120 kV and 1000 μA. The image enhancement was later performed using ImageJ, which involves the process of aligning the image contrast, edge enhancement, processing histogram value, and adjusting image colors. The resulted data were costumized according to the information to be obtained from the digital X-ray radiography test such as dimensional data, boundaries between pellet, and histogram ilustrating material or thickness differences. Further, this information can be used as data input in mapping the concept of enhancement of image of short pin PWR fuel contains UO2 pellets. Output image produced from the enhancement process not only has a better resolution and quality to facilitate the process of analysis and interpretation but also can be used as a standard method to perform image enhancement of digital X-ray radiography images of short pin PWR fuel contains UO2 pellets after irradiation.
KARAKTERISASI MIKROSTRUKTUR, KEKERASAN, KOMPOSISI KIMIA DAN STRUKTUR KRISTAL LAPISAN PADA PERMUKAAN BAJA Sungkono; Maman Kartaman Ajiriyanto; Sri Ismarwanti; Rohmad Sigit
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): 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.2019.25.3.5708

Abstract

Steel and alloys are used as structural material for nuclear reactor components and supporting equipments of hot cells. During the operation of nuclear reactors or hot cell facilities, structural materials suffer from tensile, compressive, and frictional stresses in high radiation environments and thus reduce the life time of the components. One solution for this issue is surface coating of steel with materials having high hardness, corrosion and wear resistance. The aim of this research is to obtain the characteristics of microstructure, thickness, hardness, chemical composition and crystal structure of layers on steel surface. The method used was observation with optical microscope for microstructure, vickers microhardness tester for hardness, spark spectrometry for chemical composition and X-ray diffractometry for crystal structure. The results shows that the base metal microstructure consists of fine equiaxial grains with ferrite and pearlite phases, where the metal-layer interface is clearly visible, and the compact and homogeneous layer has an average thickness of 624.071 µm. The hardness of the layer is 943 VHN. From the chemical composition it is identified that the base metal is S45C carbon steel, and the surface layer is a stable compound of chromium oxide (Cr2O3) with hexagonal crystal structure.
KARAKTERISTIK MEKANIK KELONGSONG BAHAN BAKAR NUKLIR TEMPERATUR TINGGI DALAM ATMOSFER GAS NITROGEN Rohmad Sigit; Sri Ismarwanti; Guswardani; Yatno Dwi Agus Susanto; Jan Setiawan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (2018): 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.2018.24.2.4422

Abstract

At Loss of Cooling Accident (LOCA) scenario, Zr-2 and Zr-4 as nuclear fuel cladding potentially exposed to air which experimentally leads to mechanical properties degradation faster than in steam environment. This study aims to determine the impact of nitrogen on the mechanical strength of cladding by minimizing other environmental influences. The Zr-2 and Zr-4 cladding was annealed under vacuum at a temperature of 500°C for one hour. It was followed by nitriding with the pressure of 1500 mbar for two hours. It was followed by natural cooling to room temperature. The results of tensile strength and microhardness testing showed that tensile strength, ductility and microhardness values increase of 12.1%, 19.2% and 28.2% for Zr-2 and 5.1%, 25% and 22.6% for Zr-4, respectively. Nitride layer was formed on the cladding surface due to interaction with nitrogen and there is no mechanical properties degradation due to nitriding process. It was caused by nitriding processes that were not followed or accompanied by oxidation processes.
ANALISIS KETIDAKPASTIAN PENGUKURAN KEKUATAN TARIK DAN ELONGASI SPESIMEN SS304 BERBENTUK RING Sri Ismarwanti; Jan Setiawan; Maman Kartaman Ajiriyanto; Rohmad Sigit
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 3 (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.2021.27.3.6567

Abstract

Uncertainty is a measure of the reliability of a measurement. One of the widely used uncertainty analysis approaches is the Guide to the expression of uncertainty in measurement (GUM). The steps for analyzing the uncertainty of a measurement have been described in detail by the GUM approach. Uncertainty analysis was carried out on tensile testing to determine the traceability of the data obtained. Tensile testing produces data in the form of tensile strength and elongation of the test material. Tensile strength is a quantity that involves the magnitude of the force and length. Elongation is the increase in length when pulling. The tensile strength of the ring-shaped sample will be affected by the cross-sectional area on both sides of the ring when a tensile stress is applied. So, to determine the uncertainty of the tensile test, an analysis of the contributors to the uncertainty is required. This paper provides an explanation of how to analyze the uncertainty of the measurement of tensile strength and elongation in a ring-shaped sample. In addition, the value of the uncertainty in the measurement of tensile strength and elongation of SS304 (in the form of a ring) will also be presented. The test results show that the average tensile strength of SS304 rings is 631.070 ± 26.976 Nmm-2 with an expanded uncertainty of 50.451 Nmm-2 at a 95% confidence level. In addition, at the same level of confidence, the average SS304 ring elongation result is 18.681% ± 2.425% with an expanded uncertainty of 2.867%. Data repetition or repeatability is the biggest contributor to the uncertainty in measuring the tensile strength and elongation of the SS304 ring.
PENGARUH HIDROGEN TERHADAP KEKUATAN TARIK KELONGSONG BAHAN BAKAR NUKLIR BERBASIS PADUAN ZIRKONIUM Rohmad Sigit; Fajar Al Afghani; Jan Setiawan; Sungkono
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 3 (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.2017.23.3.3648

Abstract

During reactor operation, zircaloy-4 (Zr-4) as fuel cladding is under an environment that can potentially cause mechanical failure, especially by the effect of cladding-hydrogen interaction. Hydrogen would diffuse and precipitate to form brittle hydrides when the solubility limit is surpassed. In this experiment, ring tensile test method was used to examine the effect of hydrides existence on tensile strength of Zr-4 cladding. The Zr-4 sample was annealed at 500 °C and 600 °C for an hour in vacuum condition and followed by hydriding with a pressure up to 1000 mbar with 3 hours holding time and slow cooling. According to ideal gas equation, hydrogen content in Zr-4 reaches about 674 ppm and 1215 ppm at hydriding temperature of 500 °C and 600 °C respectively. Microstructure observation shows that hydrides precipitate was formed at grain boundaries. The hydrides were found to be longer and thicker at higher hydriding temperature. As the hydrogen content increases, the ring tensile test shows increasing stress at 4.4 %, decreasing strain at 2.1 % and increasing microhardness level at 13 %. This result confirms that the existence of hydrides precipitates in cladding has an effect of increasing the tensile strength and decreasing the ductility obviously.
PENGUKURAN BERAT RADIONUKLIDA 137Cs DALAM LARUTAN PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PASCA IRADIASI DENGAN METODE KOLOM KROMATOGRAFI Boybul; Yanlinastuti; Erlina Noerpitasari; Juan Carlos Sihotang; Helmi Fauzi Rahmatullah; Arif Nugroho; Mohammad Sukron Fajrin Husein; Rohmad Sigit; Aslina Br Ginting; Susilo WIdodo
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.2024.8678

Abstract

The burn up value of the fuel is one of the parameters that must be known in the post-irradiation examination. The determination of burn up aims to determine the performance of U3Si2/Al fuel after being used in the reactor. One of the isotops that can be used as an indicator of burn up is 137Cs because it has a long half-life (T1/2) of 30.17 years with a fission yield of 6.26%. Therefore, in this study, a separation was carried out to determine the amount of 137Cs in the U3Si2/Al fuel solution post irradiation using the cation exchange column method using zeolit from Lampung along with its recovery rate. The solution of irradiated U3Si2/Al fuel from Top (T), Middle (M), and Bottom (B) position, was each pipetted in a duplicate manner (duplo) in an amount of 50 µL and added with 2 mL of 0.1 M HNO3. The solutions were then measured activity using a gamma spectrometer to obtain the initial weight of 137Cs radionuclide. The solution was then inserted into a chromatography column containing 700 mg of zeolit Lampung and allowed to flow under vacuum condition. The separation results showed that 137Cs was bound to the zeolit in the form of 137Cs-zeolit solid phase, while other isotops remained in the liquid phase. The solid 137Cs-zeolit and 137Cs in the supernatant were then measured with a gamma spectrometer to determine the weight of 137Cs bound to the zeolit. The measurement results showed that the average initial weight of 137Cs (before separation) were 7.49 × 10-3 µg/gFEP and dan 6.97 × 10-3 µg/gFEP for T1 and T2 from top section, 10.50 × 10-3 µg/gFEP for M1 from Middle section, and dan 8.43 × 10-3 µg/gFEP and 8.76 × 10-3 µg/gFEP for B1 and B2 from Bottom section, respectively. After separation, the average weight of 137Cs were 7.43 × 10-3 µg/gFEP and 6.82 × 10-3 µg/gFEP for T1 and T2, 10.10 × 10-3 µg/gFEP for M1, and 8.32 × 10-3 µg/gFEP and 8.41 × 10-3 µg/gFEP for B1 and B2, respectively. From the weight of 137Cs before and after separation, the average separation recovery with the cation exchange chromatography column method using zeolit was obtained at 97.748%. This recovery value indicates that zeolit Lampung is highly selective for absorbing 137Cs in the solution of irradiated U3Si2/Al fuel.
Co-Authors Anissa Isnaini ARIF NUGROHO Aslina Br Ginting Boybul Erlina Noerpitasari Fajar Al Afghani Guswardani Helmi Fauzi Rahmatullah Jan Setiawan Juan Carlos Sihotang Maman Kartaman Ajiriyanto Maman Kartaman Ajiriyanto Mohammad Sukron Fajrin Husein Refa Artika Saga Octadamailah Sri Ismarwanti Sri Ismarwanti Sungkono Susilo WIdodo Tri Yulianto Yanlinastuti Yatno Dwi Agus Susanto