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PENGARUH TEMPERATUR DAN KOMPOSISI Nb TERHADAP INTERDIFUSI PADUAN U-Zr-Nb Maman Kartaman Ajiriyanto; Masrukan Masrukan; Fajar Al Afghani; Yanlinastuti Yanlinastuti
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 27, No 3 (2021): Oktober, 2021
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.3.6503

PENGARUH TEMPERATUR DAN KOMPOSISI Nb TERHADAP INTERDIFUSI PADUAN U-Zr-Nb. Telah dilakukan simulasi percobaan intermik bahan bakar U-Zr-Nb dengan pelat aluminium. Mula-mula dibuat ingot paduan U-6Zr-2Nb, U-6Zr-5Nb, dan U-6Zr-8Nb menggunakan tungku peleburan busur listrik. Ingot yang diperoleh dipotong-potong menjadi berukuran ketebalan 2-3 mm dan diameter sekitar 5-6 mm selanjutnya ditutup menggunakan pelat Al pada salah satu sisinya serta dipress. Setelah dipress, ingot paduan U-6Zr-2Nb, U-6Zr-5Nb, dan U-6Zr-8Nb dipanaskan pada temperature 350 dan 450 °C selama 1 jam. Setelah dipanaskan ingot dikenai beberapa pengujian yaitu mikrostruktur menggunakan mikroskop optik dan Scanning Electron Microscope (SEM) yang dilengkapi dengan Energy Dispersive Spectrometer (EDS), kekerasan menggunakan uji kekerasan mikro, dan fasa dengan alat X-ray diffractometer (XRD). Hasil pemeriksaan mikrostruktur menunjukkan masih terlihat dengan jelas batas antara lapisan (interface) U-6Zr-2Nb, U-6Zr-5Nb, dan U-6Zr-8Nb dengan lapisan Al. Semakin tinggi kandungan Nb semakin rapat rapat interface antara kedua lapisan. Pada pengujian kekerasan mikro terlihat bahwa kekerasan pada interface sulit diukur sedangkan pada daerah U-Zr-Nb menunjukkan kenaikan kekerasan pada pemanasan dari 350 menjadi 450 °C, sedangkan pada bagian Al terjadi penurunan kekerasan pada kenaikan temperatur pemanasan dari 350 menjadi 450 °C. Terbentuk senyawa UO3 pada semua sampel uji sedangkan fasa γ-U terbentuk pada sampel U-6Zr-2Nb baik yang dipanaskan pada temperatur 350 maupun 450 °C.Kata kunci: Intermik, paduan U-Zr-Nb, aluminium, mikrostruktur, kekerasan, fasa.

Nichrome Dependency in Welding Layer Using In situ Fabrication on Hardness and Corrosion Properties Syaripuddin; Sopiyan; Muhammad Fauzan Perdana Putra; Maman Kartaman Ajiriyanto; Sigit Dwi Yudanto; Muhammad Yunan Hasbi; Susetyo, Ferry Budhi
Science and Technology Indonesia Vol. 9 No. 3 (2024): July
Publisher : Research Center of Inorganic Materials and Coordination Complexes, FMIPA Universitas Sriwijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26554/sti.2024.9.3.651-659

The use of shielded metal arc welding (SMAW) equipment to synthesize alloys is one of the most promising methods as it can be used for in-situ fabrication. The hardness and corrosion properties of the deposited layer during the welding process can be enhanced by dilution of nichrome (NiCr) during the process. Therefore, the alloy was synthesized on the surface of the mild steel using SMAW equipment with various NiCr additions. The properties of the alloy were investigated using an X-ray diffraction (XRD), an Optical microscope, a Potentiostat, and a Vickers hardness apparatus. The appearance of martensite overlaps with the ferrite phase could be affected by the addition of NiCr to the alloy. An increase in NiCr content is followed by an increase in the lattice parameter value of the ferrite phase. The presence of a certain amount of nickel (Ni) contributes to the formation of lower transformation phases, including martensite. At the same time, the incorporation of chromium (Cr) also plays a significant role in promoting the formation of acicular ferrite. An increase in NiCr content in NiCr2 and NiCr3 samples results in a quantitative increase in martensite formation. Adding 0.434 g of NiCr to the weld deposited layer could result in the corrosion rate of the alloy being 0.1118 mm/y. Higher hardness is found in the NiCr3 sample, around 742.06 HV.

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

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

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.

ANALISIS KOROSI PIPA PENDINGIN SEKUNDER RSG-GAS DENGAN TEKNIK ELECTROCHEMICAL IMPEDANCE SPECTROSCOPY (EIS) Maman Kartaman Ajiriyanto; Rosika Kriswarini; Yanlinastuti Yanlinastuti; Diyah Erlina Lestari
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.2018.24.2.4421

Multi-purpose reactor G.A. Siwabessy has a secondary cooling system facility to extract heat generated from uranium fission reactions in the reactor. The cooling pipe material is a type of carbon steel. Secondary cooling media is water supplied from Puspiptek. To extend the lifetime of the pipe, chemical compound ZnPO4 was put on the water-cooling media as a corrosion inhibitor. The corrosion analysis of secondary pipe was performed by corrosion testing using EIS and tafel method. The electrochemically corrosion test was performed with three electrode cells in water media, 0.05 M HCl solution and 3% NaCl solution. The aim is to obtain the optimum inhibitor concentration added in the secondary coolant and to determine the inhibition mechanical as well as the inhibitor efficiency. EIS testing was performed in the frequency range 100 kHz to 0.02 Hz in HCl 0,05M. Test results show changes in electrical parameters such as Rct, Cdl and Rs. The inhibitor concentration increases then Rct value increase. At inhibitor concentration of 90 ppm obtained the highest Rct value is 81,29 ohm. Efficiency of the inhibitor addition produces maximum value is 66,75% at concentration of 90 ppm. The corrosion rate in samples on medium of 3% NaCl without inhibitor, moss inhibitor and corrosion inhibitor were 3.975, 3.576 and 3.215 mpy respectively. The addition of a mixture of corrosion inhibitors and moss inhibitors can decrease the corrosion rate up to 1.586 mpy quantitatively. The addition of inhibitors using ordinary water may inhibit interface reactions on the surface of the sample as indicated by the higher the inhibitor concentration the higher the Rct value. In NaCl 3% medium also shows the same phenomenon relatively that the corrosion mechanism can be inhibited by increasing of Rct value as well as in this condition, Rs value is constant relatively. The dominant fact that the addition of a corrosion inhibitor could decrease the corrosion rate. The moss inhibitors have a primary function not to decrease the corrosion rate.

ANALISIS METALOGRAFI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 2,96 gU/cm3 PASCA IRADIASI Maman Kartaman Ajiriyanto; Aslina Br. Ginting; Junaedi
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 1 (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.2018.24.1.4010

Metallographic analysis of U3Si2/Al fuel element plate has been performed in hot cell. The purpose of metallographic analysis is to study changes in PEB U3Si2/Al microstructure and AlMg2 cladding thickness after irradiation in reactor until burn up of 56%. The fuel element plate of irradiated U3Si2/Al was cut in top, middle and bottom positions with each size around 5x5x1,37mm. Metallographic preparation starts from sample cutting using cutting machine with low speed and sample mounting, grinding and polishing in hot cell 104–105. Sample mounting was done by using resin for more than 10 hours followed by grinding with sandpapers up to grit size of 2400 and polishing with diamond paste of size 3 to 1 micron at a rotational speed of 150 rpm for 5 minutes. Microstructure observation was performed with optical microscope in hot cell 107 at 200 times magnification. Microstructure examination reveals U3Si2 particles with diverse forms and sizes, Al matrix and AlMg2 cladding were spread along the U3Si2/Al side. Microstructure observation of irradiated U3Si2/Al has not shown good result because only topography observation of U3Si2/Al meat, Al matrix and AlMg2 cladding can be done due to limited capability of the optical microscope in hot cell, where maximum magnification can be attained only at 200 times so that the phenomenon of interaction layer and small gas bubble cannot be observed. However, U3Si2/Al microstructure of 56% burnup, if compared to the microstructure of U3Si2/Al fuel element plate of 60% burnup from previous researcher, shows interaction between U3Si2 meat with Al matrix and the existence of layers with a thickness about 5 up to 20 microns. Meanwhile, the observed thickness of AlMg2 cladding is greater than 0.25 mm, which indicates that irradiation does not significantly change the thickness of AlMg2 cladding so that the overall irradiated U3Si2-Al still has good integrity and stability.

PENGARUH TEMPERATUR DAN KOMPOSISI Nb TERHADAP INTERDIFUSI PADUAN U-Zr-Nb Maman Kartaman Ajiriyanto; Masrukan; Fajar Al Afghani; Yanlinastuti Yanlinastuti
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.2021.27.3.6503

A simulation of U-Zr-Nb intermixed fuel has been carried out with aluminum plates. Initially, U-6Zr-2Nb, U-6Zr-5Nb, and U-6Zr-8Nb alloy ingots were made using an electric arc melting furnace. The ingot obtained was cut into pieces with a thickness of 2-3 mm and a diameter of about 5-6 mm, then it was covered Al plate on one side and pressed. After pressing, the alloy ingots of U-6Zr-2Nb, U-6Zr-5Nb, and U-6Zr-8Nb were heated at temperatures of 350 and 450 oC for 1 hour. The ingot was subjected to several tests, namely microstructure examination using optical microscope and Scanning Electron Microscope (SEM) equipped with Energy Dispersive Spectrometer (EDS), hardness test using microhardness tester, and phase observation using X-ray diffractometer (XRD). The results of microstructure examination show that the boundaries between the U-6Zr-2Nb, U-6Zr-5Nb, and U-6Zr-8Nb layers (interfaces) and the Al layer were clearly visible. The higher of the Nb content, the denser the interface between the two layers. For the microhardness test, we found that the hardness at the interface was difficult to measure, while the U-Zr-Nb region shows an increase in hardness for heating from 350 to 450 oC, while in the Al section there is a decrease in hardness when the heating temperature increases from 350 to 450 oC. UO3 compounds were formed in all test samples while the γ-U phase was formed in U-6Zr-2Nb samples both heated at temperatures of 350 and 450 oC.

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

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.

ANALISIS KOROSI PADUAN ZIRLO-Mo DALAM MEDIA NaCl MENGGUNAKAN METODE POLARISASI Maman Kartaman Ajiriyanto; Dian Anggraini; Rosika Kriswarini
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.2017.23.3.3221

Zirlo-Mo is a zirconium type of alloy, which is developed as cladding material for light water reactor. As cladding material, the important parameter to be characterized is its corrosion resistance properties. The goal of this research is to study the corrosion resistance of zirlo-Mo in NaCl medium with varied concentration of 0.03; 0.3; and 3 % and compare it to the those of zircaloy-2 dan zircaloy-4 in the same medium. Samples were mounted into disk form and metallographically prepared, i.e. treatment with abrasive paper of 500 to 1200 grit SiC. The analysis of zirlo-Mo corrosion rate was performed by polarization method with a potentiostat. The advantage of this polarization resistance method is that it takes shorter testing time if compared to weight gain method, and it can be applied to analysis at low corrosion rate of below 0.1 mpy. Other tests were also done to support the corrosion rate analysis such as microhardness test with microhardness tester and microstructure examination with optical microscope. The tests results show that in general zirlo-Mo, zircaloy-2 and zircaloy-4 possess very low corrossion rate, i.e. below 1 mpy. The corrosion rate of zircaloy-2, zircaloy-4 and zirlo-Mo in NaCl 3 % medium are 0.006; 0.007 and 0.590 mpy respectively. The corrosion rate of zirlo-Mo is relatively the highest due to its lath martensite or accicular structure, which has high hardness value. The lath martensite structure and high hardness properties make zirlo-Mo highly susceptible to corrosion. Hardness test results show that the hardness value of zircaloy-2, zircaloy-4 and zirlo-Mo are 194.79; 227.95 and 360.05 HV respectively. The existence of solid solution of Mo and Zr-α as well as the martensite or acicular structure of zirlo-Mo result in high hardness value of the alloy.

PENGARUH TEMPERATUR DAN IRADIASI TERHADAP INTERDIFUSI PARTIKEL BAHAN BAKAR JENIS U−7Mo/Al Maman Kartaman Ajiriyanto; Aslina Br. Ginting; Supardjo; Boybul Boybul
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 1 (2016): 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.2016.22.1.2740

U−7Mo/Al alloy had great potential as research reactor fuel, but it had several disadvantages, such as, it can form a interaction layer at the interface during the process of fabrication and irradiation in a reactor. The research objective was determining the interaction layer that was caused by interdiffusion or diffusion couple of U−7Mo with AlMg2 alloy which was annealed at 500 °C and 550 °C for 24 hours. The observation of microstructure used a Scanning Electron Microscope (SEM) on diffusion couple sample which was heated at temperature of 500 °C had not seen the layer interaction or the formation of a new phase between particles of U−Mo and Al matrix, but heating treatment at 550 °C indicated that U−7Mo alloy had been interdiffusion with AlMg2 plate produced (U,Mo) Alx compound on the interfaces. It was evidenced by interdiffusion reaction analysis used DTA that showed that U−7Mo / Al alloy at 500 °C had good heat compatibility, but at temperatures upper than 550 °C it had been phase changed from a + d to a + g phase. The heating in DTA furnace up to 679.14 °C produced U(Al,Mo)x meta stable phase and then interdiffusion process with uranium molten formed layer interaction that formed UAlx compound agglomerates (UAl4, UAl3 and UAl2). Agglomerates was formed from the heating process which was similar to agglomerates that caused by irradiation. U−7Mo / Al Fuel alloy that had 58% burn up had been interdiffusion between U−7Mo with Al matrix produced U(Al,Mo)x metastable phase that turned into (U, Mo) Al7 layer, UMo2Al20 precipitates, (UMo)Al3−Al and formed a boundary or UAlx (UAl4, UAl3 and UAl2) agglomerates. The results of microstructure analysis used SEM and interdiffusion reactions used DTA was supported by the analysis of micro hardness used Vickers Hardness. The results of hardness analysis that was done to AlMg cladding and U−7Mo alloy (before and after heating) and diffusion couple of U−7Mo / Al samples with AlMg2 plate after heating at 550 °C were respectively 64.62 and 340.45 HV (before heating) and 52.34; 303.16 and 497.34 HV (after heating). Diffusion couple U−7Mo/Al with AlMg2 plate samples had the highest hardness value. This hardness difference showed that the interdiffusion test used diffusion couple produced a new compound (U, Mo) Alx in interface zone that had different character, but the formation of interaction layer is not expected in the fuel U−Mo / Al dispersion because micro hardness and density of (U, Mo) Alx compound’s layer was lower than the average density of U−7Mo/ Al alloy.

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